JP2013510314A - Method and system for moving a nuclear fuel assembly in a fission reactor - Google Patents

Abstract

  Exemplary embodiments include a method and system for moving a nuclear fuel assembly in a nuclear fission reactor, a method for operating a traveling wave fission reactor, a method for controlling a traveling wave fission reactor, a control system for a traveling wave fission reactor, a progression A computer software program product for controlling a wave fission reactor and a traveling wave fission reactor having a system for moving a nuclear fuel assembly are provided.

Description

Detailed Description of the Invention

〔background〕
The present application relates to a method and system for migrating nuclear fuel assemblies in a fission reactor.

[Cross-reference for related applications]
This application relates to and claims the benefit of the earliest effective filing date based on the applications listed below (“Related Applications”). For example, this application may claim the earliest effective priority date other than the provisional patent application, or any provisional patent application, any parent application of the related application, its parent application, and its parent application, etc. Claims a benefit under 35 USC §119 (e). All contents of the related application, including any priority application, including any priority application, its parent application, and also its parent application, including priority, are hereby incorporated by reference to the extent that they do not conflict with this specification. Incorporated into the book.

[Related applications]
Due to the special legal requirements of the USPTO, this application is entitled “METHODS AND SYSTEMS FOR MIGRATING FUEL ASEMBLIES IN A NUCLEAR FISSION REACTOR (Method and System for Moving Nuclear Fuel Assemblies in Fission Reactors)” Serial No. 12 / 590,448 (inventor: Ehud Greenspan, Roderick A. Hyde, Robert C. Petroski, Joshua C. Walter, Thomas Allan Weaver, Charles Whir. Charles Low. George B. Zimmerman, filed Nov. 6, 2009, currently co-pending) or currently A application right to the benefit of the filing date application are co-pending is given.

  Due to the special legal requirements of the USPTO, this application is entitled “METHODS AND SYSTEMS FOR MIGRATING FUEL ASEMBLIES IN A NUCLEAR FISSION REACTOR (Method and System for Moving Nuclear Fuel Assemblies in Fission Reactors)” Serial No. 12 / 657,725 (inventor: Ehud Greenspan, Roderick A. Hyde, Robert C. Petroski, Joshua C. Walter, Thomas Allan Weaver, Charles Whir. Charles L., Well. George B. Zimmerman, filed January 25, 2010, currently co-pending) Or a application right to the benefit of the filing date is given in the application that is currently co-pending.

  Due to the special legal requirements of the USPTO, this application is entitled “METHODS AND SYSTEMS FOR MIGRATING FUEL ASEMBLIES IN A NUCLEAR FISSION REACTOR (Method and System for Moving Nuclear Fuel Assemblies in Fission Reactors)” Serial No. 12 / 657,726 (inventor: Ehud Greenspan, Roderick A. Hyde, Robert C. Petroski, Joshua C. Walter, Thomas Allan Weaver, Charles Whir. Charles L. Well. George B. Zimmerman, filed January 25, 2010, currently co-pending) Or a application right to the benefit of the filing date is given in the application that is currently co-pending.

  Due to the special legal requirements of the USPTO, this application is entitled “METHODS AND SYSTEMS FOR MIGRATING FUEL ASEMBLIES IN A NUCLEAR FISSION REACTOR (Method and System for Moving Nuclear Fuel Assemblies in Fission Reactors)” Serial No. 12 / 657,725 (inventor: Ehud Greenspan, Roderick A. Hyde, Robert C. Petroski, Joshua C. Walter, Thomas Allan Weaver, Charles Whir. Charles L., Well. George B. Zimmerman, filed January 25, 2010, currently co-pending) Or a application right to the benefit of the filing date is given in the application that is currently co-pending.

  The US Patent and Trademark Office (USPTO) requires the patent applicant to refer to the serial number in the USPTO computer program and indicate whether the application is ongoing, partly ongoing, or a division of the parent application Announced a notice about that. This is because Stephen G., entitled “Profit of the Prior Application”. Notification by Kunin (USPTO official gazette on March 18, 2003), http: // www. uspto. gov / web / offices / com / sol / og / 2003 / week11 / patbene. htm. It can be browsed at. The applicant organization of the present application (hereinafter “applicant”) provides above specific references to applications for which priority is claimed in accordance with law. Applicants are unambiguous in the wording of the specific reference indicated by the statute and may have any reference number or any feature such as “ongoing” or “partially ongoing” to claim priority of a US patent application. I understand that I do not need it. However, since the applicant understands that the USPTO computer program has certain data entry requirements, the relationship between the present application and its parent application is displayed as described above. It should not be construed as any note and / or admission as to whether any new matter is included in addition to the matter contained in the parent application.

〔wrap up〕
Exemplary embodiments include a method and system for moving a nuclear fuel assembly in a nuclear fission reactor, a method for operating a traveling wave fission reactor, a method for controlling a traveling wave fission reactor, a control system for a traveling wave fission reactor, a progression A computer software program product for controlling a wave fission reactor and a traveling wave fission reactor having a system for moving a nuclear fuel assembly are provided.

  The above summary is exemplary only and is not intended to be limiting in any way. In addition to the illustrative aspects, embodiments, and features described above, further aspects, embodiments, and features will become apparent by reference to the drawings and the following detailed description.

[Brief description of the drawings]
FIG. 1A is a block diagram of an exemplary method of operating a traveling wave fission reactor.

  1B-1D are perspective views of some schematic configurations of core components of an exemplary fission reactor.

  1E-1H illustrate the effect of the combustion wavefront shape of the fission traveling wave due to the movement of selected fission fuel subassemblies.

  FIG. 1I is a block diagram detailing a portion of the method of FIG. 1A.

  FIG. 1J shows the rotation of the fission fuel subassembly.

  FIG. 1K is a block diagram detailing a portion of the method of FIG. 1A.

  FIG. 1L shows inversion of the fission fuel subassembly.

  1M-1N are block diagrams detailing a portion of the method of FIG. 1A.

  FIG. 1O shows the spiral movement of the fission fuel subassembly.

  FIG. 1P is a block diagram detailing a portion of the method of FIG. 1A.

  FIG. 1Q shows the axial movement of the fission fuel subassembly.

  FIG. 1R shows a substantially spherical shape of the combustion wavefront of the fission traveling wave.

  FIG. 1S shows a continuous curved surface shape of the combustion wavefront of the fission traveling wave.

  FIG. 1T shows a substantially rotationally symmetric shape of the combustion wavefront of the fission traveling wave.

  1U-1V show the approximately n-fold rotationally symmetric shape of the combustion wavefront of the fission traveling wave.

  FIG. 1W shows the asymmetric shape of the combustion wavefront of the fission traveling wave.

  1X-1AF are block diagrams detailing a portion of the method of FIG. 1A.

  FIG. 2A is a block diagram of an exemplary control method for a traveling wave fission reactor.

  2B-2M are block diagrams detailing a portion of the method of FIG. 2A.

  FIG. 3A is a block diagram of an exemplary system for determining movement of a fission fuel subassembly.

  3B-3C are block diagrams detailing the components of the system of FIG. 3A.

  FIG. 4A is a block diagram of an exemplary system for moving a fission fuel subassembly.

  4B-4C are block diagrams detailing the components of the system of FIG. 4A.

  FIG. 5 is a block diagram of a partial schematic configuration of an exemplary traveling wave fission reactor.

  FIG. 6A is a flowchart of an exemplary method of operating a traveling wave fission reactor.

  FIG. 6B is a block diagram detailing a portion of the method of FIG. 6A.

  FIG. 7 is a flowchart of an exemplary method of operating a traveling wave fission reactor.

  FIG. 8 is a flowchart of an exemplary method of operating a traveling wave fission reactor.

  FIG. 9 is a flowchart of an exemplary method of operating a traveling wave fission reactor.

  FIG. 10A is a flowchart of an exemplary method of operating the fission reactor.

  10B-10D are block diagrams detailing a portion of the method of FIG. 10A.

[Detailed explanation]
In the following detailed description, reference will be made to the accompanying drawings, which form a part hereof. In the above drawings, similar symbols typically identify similar components, unless context dictates otherwise. The illustrative embodiments described in the detailed description, drawings, and claims are not meant to be limiting. Other embodiments may be utilized and other changes may be made without departing from the spirit or scope of the matters presented herein.

  Exemplary embodiments include a method and system for moving a fuel assembly in a fission reactor, a method for operating a fission traveling wave reactor, a method for controlling a fission traveling wave reactor, a system for controlling a fission traveling wave reactor, a fission traveling wave A fission traveling wave reactor having a computer software program product for controlling the reactor and a system for moving the fuel assembly is provided.

(Outline of fission traveling waves)
Before the details of the non-limiting embodiments shown herein are explained, an overview of fission traveling waves is given. The fission traveling wave is also known as a fission deflagration wave, but for the purpose of clarity, reference is made to the fission traveling wave in this specification. The following discussion is part of a paper that is hereby incorporated by reference in its entirety: Completely Automated Nuclear Power Reactors For Long-Term Operation: III. Enabling Technology For Large-Scale, Low-Risk, Affordable Nuclear Electricity ”by Edward Teller, Muriel Ishikawa, Lowell Wood, Roderick Hyde, and John Nuckolls, presented at the July 2003 Workshop of the Aspen Global Change Institute, University of California Lawrence Livermore National Laboratory publication UCRL-JRNL-122708 (2003). , The International Journal, prepared for posting in 30 November 2003).

  In a “wave” that travels through the core of the fission traveling wave at a rate on the order of 1 centimeter per year, the fission fuel parent material is propagated to the fission fuel material and then undergoes fission.

  Certain fission fuels (eg, without limitation, uranium, thorium, plutonium, or even pre-burned fission fuel assemblies) for use in a fissioning traveling wave reactor, It is typically widely available. Also, other fission fuels that are not widely used (eg, without limitation, other actinides or their isotopes) may be used. Some fissioning traveling wave reactors are intended for long-term operation at full power, ranging from about 1/3 century or more than 1/2 century. Some fission-wave reactors are not intended for refueling (but instead are intended for on-site burial at the end of their life. Some fission-wave reactors are out of service. Refueling of nuclear fuel is intended, with several replenishment of nuclear fuel and several replenishment of nuclear fuel during power supply operation, and the regeneration of fission fuel is avoided, thereby diverting it to military use and It is intended that the potential for other problems can be reduced.

  The simultaneous consideration of achieving 1/3 to 1/2 century (or more) operation at full power without nuclear fuel replenishment and avoiding fission fuel regeneration is the use of fast neutron spectra. You may need it. In addition, propagating fission traveling waves can be achieved with an average high combustion of non-enriched actinide fuels (eg natural uranium or thorium) and isotopically moderately enriched fissionables in the core loading fuel Enables the use of relatively small “fission igniters” of simple materials.

  Thus, a fission traveling wave core may suitably include a fission igniter and a larger propagation region of fission deflagration. The propagation region of the fission deflagration wave preferably contains thorium or uranium fuel, and preferably functions based on the principle of fission multiplication in the fast neutron spectrum.

The fission traveling wave reactor is preferably a breeder reactor because of the efficient utilization of nuclear fuel and the minimization of the need for isotope enrichment. Furthermore, the large absorption cross-section of the fission product for thermal neutrons produces a high utilization of thorium fuel, or a higher utilization of fuel of the more abundant uranium isotope U ²³⁸ in embodiments fueled with uranium. Fast neutron spectra are preferably used because they do not allow without removal of objects.

  An illustrative fission traveling wave will now be explained. Propagation of deflagration waves through the fission fuel material can emit power at a predictable level. Furthermore, if the above composition of material has time independent characteristics (eg, the composition found in each typical reactor that produces industrial power), the subsequent power generation is stable. Can be a level. Finally, if the traveling wave propagation velocity can be adjusted externally in a particular manner, the energy release rate and thus the output generation can be controlled as desired.

  Nuclear engineering of traveling fission waves is explained below. Promoting fission of selected isotopes of actinide elements (ie fissionable isotopes) by absorption of neutrons of any energy will result in the release of nuclear binding energy at any material temperature (including any low temperature). Acceptable. Neutrons absorbed by the fissile actinide element can be provided by a fission igniter.

On average, more than one neutron emission per absorbed neutron by fission of virtually any isotope of an actinide may provide an opportunity to branch into a neutron-mediated fission chain reaction in such materials. The number of neutrons released for each absorption is specified as η (where η = υσ _f / (σ _f + σ _c ), where υ is the number of neutrons released for each split). The release of more than two neutrons for each neutron absorbed (on average exceeds a certain range of neutron energy) is caused by initial neutron capture to first convert a non-split isotope atom to a fissile isotope atom ( Conversion (via neutron capture and subsequent beta decay), and then allowing neutron fission of the newly generated fissionable isotope nuclei in the course of the second neutron fission absorption.

  On average, from a given fission event, one neutron can be radiatively captured by a non-fissionable nucleus that can be converted to a fissile material that is later converted into a fissionable nucleus (eg, via beta decay), and the same The highest Z (Z ≧ 90) nuclide is the fission fuel material in a traveling wave reactor (ie breeder reactor) when the second neutron from the fission phenomenon is trapped in the fissionable nucleus and thus can cause fission Can be used as In particular, when these arrays are in a steady state, sufficient conditions for propagating fission traveling waves in a given material can be satisfied.

Due to the beta decay of intermediate isotopes in the process of converting nuclei that can be converted to fissionable materials into fissionable nuclei, the rate at which fissile materials are useful for fission is limited. Thus, the inherent speed of a traveling wave is limited by a half-life on the order of days or months. For example, the inherent velocity of the traveling wave is from the birth of its fission to the half-life of the beta decay (the longest remaining nucleus in the chain) leading to a fissionable nucleus into a fissionable nucleus It can be up to the ratio of the distance traveled by the neutrons before the radiation capture by the nuclei that can be converted into matter. The intrinsic transport distance of splitting neutrons in standard density actinides is about 10 cm and the half-life of β decay is 10 ⁵ to 10 ⁶ seconds for the most interesting case. According to some designs, the inherent velocity of the wave is 10 ⁻⁴ to 10 ⁻⁷ cm · sec− ¹ . Such relatively slow traveling speeds indicate that the waves can be characterized as traveling waves (ie deflagration waves) rather than detonation waves.

  When trying to accelerate the wave, the tip of the wave touches a very pure material (relatively lossy with respect to neutrons) that can be converted into fissionable material, and a lot in front of the center of the wave Dramatically lower with respect to concentration. The tip of the wave (referred to herein as the “combustion wavefront”) stalls or slows down. Conversely, if the wave decelerates and the conversion rate is maintained above 1 (ie, the growth rate exceeds the division rate), then the locality of the fissionable nucleus resulting from continued beta decay As the concentration increases, the local rate of fission and neutron production increases, and the wave tip (ie, the combustion wavefront) accelerates.

  Finally, propagation can occur at any low temperature if the fission-related heat is removed sufficiently and rapidly from the entire composition of the wave-propagating material that can be converted to fission material initially. However, the temperature of both neutrons and splitting nuclei can be about 1 MeV.

Conditions for inducing and propagating fission traveling waves can be realized using readily available materials. The fissionable isotopes of actinide elements are absolute and relatively rare relative to the fissionable isotopes of these elements, the fissionable isotopes are condensed and enriched, Can be synthesized. For example, the use of both naturally occurring fissionable isotopes and artificial fissionable isotopes (eg, U ²³³ , ²³⁵ U and ²³⁹ Pu, respectively) in the initiation of fission is well known.

An appropriate cross-sectional consideration of neutrons is that if the neutron spectrum in the wave is a “highly transmissible” spectrum or a “fast” spectrum, the fission traveling wave is a naturally occurring actinide (eg, ²³² Th or ²³⁸ U) can burn most of the nuclei. In other words, when the neutrons that convey the chain reaction in the waves have energies that are not very small compared to about 1 MeV, where neutrons are evaporated from the initial fission residue, A relatively large loss to the economy is when the local majority of the fission product is commensurate with the bulk of the material that can be converted to fission material (one mole of fissile material is the nucleus of two moles of fission product. Can be avoided). The neutron loss of a standard structural material (eg, Ta) of a neutron reactor that has the desired high temperature properties becomes important at neutron energies of 0.1 MeV or less.

  Other considerations are the (relatively low) variation in incident neutron energy of splitting neutron multiplicity ν, and the percentage of all neutron absorption events (not just γ-ray emission based on neutron capture) that cause splitting α. The algebraic code of the function α (ν−2) constitutes a condition for the possibility of propagation of fission traveling waves in a material that can be converted into a fission material. The possibility is that the total amount of fissionable isotope mass used for each of the fissionable isotopes in the core in the absence of neutron leakage due to parasitic absorption in the core or core body (eg by fission products) Have been compared. The algebraic sign is generally positive for all of the given fissionable isotopes that fall from the neutron energy of about 1 MeV splitting into the resonant capture region.

  The quantity α (ν−2) / ν is capped at the ratio of total neutrons that can be lost resulting from fission to leakage, parasitic absorption or geometrical divergence during traveling wave propagation. This ratio is over the neutron energy range (approximately 0.1-1.5 MeV) that dominates in all of the actual predetermined configurations of the actinide isotopes that are not effectively decelerated, for the splitting major isotopes. Note that it is between 0.15 and 0.30. Parasitic losses due to fission products determine the conversion from fissionable material to fissionable by a rough estimate of 1 to 1.5, and the dominant situation for thermal (external) energy neutrons In contrast, the generation of fissionable elements based on capture by isotopes that can be converted to fission material is the generation of fission with an estimated value of 1.5 over a neutron energy range of 0.7 to 0.1-0.5 MeV. It is advantageous over the capture of objects. The former shows that the conversion from fissionable material to fissionable is only possible for the thermal neutron energy range of about 1.5-5%, the latter shows that more than 50% conversion is possible. It shows what can be expected about the neutron spectrum around the splitting energy.

In view of the conditions of propagation of fission traveling waves, in some approaches, neutron leakage can be substantially ignored due to the very large “self-reflecting” actinide configuration. Traveling wave propagation is a sufficiently large composition of two relatively abundant actinides on the ground ( ²³² Th and ²³⁸ U, respectively, the main and only components of the naturally occurring thorium and uranium isotopes). It is fully understood that can be realized in

The transport of split neutrons in these isotopes of actinides before the neutron energy is significantly below 0.1 MeV (which makes it susceptible to negligible potential for fission product capture by the nucleus). This produces either nuclei that can be converted to fission material or capture by fissionable nuclei. Fission product nuclei concentrations can be similar or in some situations that exceed the concentration of fissionable materials and fissionable nuclei, production convertible to fission products or fissionable materials It is well understood that it may be an approximation below the lesser of the objects. Appropriate neutron scattering cross-section considerations are that a sufficiently large actinide configuration is substantially infinitely thin (ie self-reflecting) for splitting neutrons in the radial dimension and a density of 200 gm / cm ² << It shows having a product with a radius (ie a radius of 10-20 cm << of the solid phase density of ²³⁸ U- ²³² Th).

  Propagation and traveling waves provide sufficient excess neutrons in the mean free path of 1-2 to unburned fuel to propagate new fissionable material and efficiently burn burned fissionable fuel in the wave Let it return. “Ashes” behind the peak of the combustion wave, because the neutron reactivity of the fissionable part is just balanced by the parasitic absorption of the structure and the inventories of the fission products to the tip of the leak Is substantially “neutronically neutral”. The center of the wave and the storage capacity of the splitting atom just before it is constant in time as the wave travels, when the wave is therefore stable and decreases as the wave travels A wave can be said to be “accelerated” when it “disappears” and increases as the wave progresses.

  Thus, a fission traveling wave can be propagated and maintained in a substantially steady-state condition over time as a naturally occurring isotope composition of an actinide.

  The above discussion shows that a fission traveling wave can be stably propagated over arbitrarily large axial distances, less than 1 meter or such diameter (with a much smaller diameter if an efficient neutron reflector is employed). Possible natural) uranium metal or thorium metal are considered for non-limiting illustration purposes. However, the propagation of fission traveling waves should not be construed as limited to cylindrical, symmetric shapes or individually connected shapes. Accordingly, further embodiments of alternative forms of a fissioning traveling wave core are described in US patent application Ser. No. 11 / 605,943 (filing date: Nov. 28, 2006), the contents of which are incorporated herein by reference. Inventor: Roderick A. Hyde, Muriel Y. Ishikawa, Nathan P. Myhrvold, and Lowell L. Wood, Jr., name: AUTOMATED NUCLEAR POWER REACTOR FOR LONG-TERM OPERATION).

  The propagation of a fission traveling wave is related to the fission traveling wave reactor embodiment. As a first example, local material temperature feedback can be applied to an acceptable spending local nuclear reaction rate in the traveling wave neutron economy. Such a large negative temperature coefficient of neutron reactivity provides the ability to control the traveling wave forward speed. If very little heat output is extracted from the combustion fuel, its temperature will rise, the temperature-dependent reactivity will decrease, the fission rate at the center of the wave will correspondingly decrease, and the wave time equation will be very Reflects only small forward shaft speeds. Similarly, if the heat removal rate is high, the material temperature will decrease, the neutron reactivity will increase, the neutron economy in the wave will be relatively undamped, and the wave will be relatively rapid relative to the axial direction. proceed. For details on an illustrative implementation of temperature feedback that can be incorporated into an embodiment of a core assembly, see US patent application Ser. No. 11 / 605,933 (filing date: 2006), the contents of which are hereby incorporated by reference. Inventor: Roderick A. Hyde, Muriel Y. Ishikawa, Nathan P. Myhrvold, and Lowell L. Wood, Jr., Name: CONTROLLABLE LONG TERM OPERATION OF A NUCLEAR REACTOR).

  As a second example of implementation of fission traveling wave progression in a fission traveling wave reactor embodiment, less than all of the total amount of fission neutron production in a fission traveling wave reactor may be utilized. For example, a reactivity control system (e.g., without limitation, a neutron absorber in a control rod or a module that regulates the local material temperature) may be about 5-10 of the total amount of fission neutron production in a fissioning progressive wave reactor. % Can be used. More than 10% of the total amount of fission neutron production in a fission traveling wave reactor is made up of high-performance, high-temperature structural materials (eg, Ta, W or Re) employed in structural components of a fissioning progressive wave reactor Can be lost due to parasitic absorption. This loss occurs in order to achieve the desired thermodynamic efficiency in the conversion to electricity and to obtain a safe figure of merit for the system. The Z of these materials (eg, Ta, W and Re) is about 80% of the actinide Z, so their radioactive capture cross section for high energy neutrons is compared to the actinide radioactive capture cross section. Especially small. The last 5-10% of the total amount of fission neutron production in a fission traveling wave reactor can be lost due to parasitic absorption in fission products. However, it can be expected that the spectrum may be similar to that of a sodium-cooled reactor that can cause about 1-2% loss. As mentioned above, about 70% of the increase in fission neutron production is sufficient to maintain traveling wave propagation in the absence of leakage and rapid shape divergence, and the neutron economy is sufficiently abundant.

  As a third example of implementation of fission traveling wave propagation in a fission traveling wave reactor embodiment, the initial fuel storage burnup (about 20% to about 30% or some In that case, about 40% or on the order of 50% to about 80%) may allow for high efficiency utilization of as-mined fuel without the need for further reprocessing.

  It is noted that the neutron flux from the most intensely burning region behind the combustion wave front propagates the fissionable isotope enriched region at the tip of the combustion wave front, thereby advancing the fission traveling wave. The After the combustion wave front of the fission traveling wave has passed through a given population of fuels, the concentration of fissionable atoms is such that the radioactive capture of neutrons by effective nuclei that can be converted into fissionable materials is greater than the radioactive capture of nuclear fissionable products It continues to rise as long as it is fairly large, and ongoing divisions produce very large amounts of fission products. The nuclear energy production density reaches its highest point at any given moment in this region of charge fuel.

  The ratio of fission product nuclei to fissionable nuclei (whose mass is on average close to half the mass of fissionable nuclei), well behind the burning wave front of the fission traveling wave It is properly understood that the value rises to a value comparable to the ratio of fissionable fission to the product's radioactive capture cross section. The “local neutron reactivity” reaches a negative value or may be negative in some embodiments. Thus, both combustion and growth are effectively stopped. Also, in some embodiments, a non-split neutron absorber (eg, boron carbide, hafnium or gadolinium) can be added to ensure that the “local neutron reactivity” is negative. Is properly understood.

  In some embodiments of a fissioning traveling wave reactor, all fission fuel that is always used in the reactor is installed during manufacture of the core assembly. Also, in some configurations, spent fuel is not removed from the core assembly. In some approaches, such embodiments may allow operation after initiation of fission, and possibly after completion of combustion wavefront propagation, without approaching the core at all.

  In some other embodiments of a fission traveling wave reactor, all fission fuel that is always used in the reactor is installed during the manufacture of the core assembly and in some configurations removed from the spent core. Not. However, as explained below, at least some of the fission fuel can be moved within the core or can be transferred within the core. Such transfer or transfer of at least some fission fuels can be performed to achieve the purpose as described below.

  However, in some other embodiments of a fission traveling wave reactor, additional fission fuel may be added to the core assembly after the initiation of fission. In some embodiments of a fission traveling wave reactor, spent fuel may be removed from the core assembly (in some embodiments, spent fuel removal may be performed during power operation of the fission traveling wave reactor. ). Such exemplary refueling and fuel removal is described in US patent application Ser. No. 11 / 605,848, the contents of which are incorporated herein by reference (filing date: November 28, 2006, inventor: Roderick). A. Hyde, Muriel Y. Ishikawa, Nathan P. Myhrvold, and Lowell L. Wood, Jr., Name: METHOD AND SYSTEM FOR PROVIDING FUEL IN A NUCLEAR REACTOR). Regardless of whether spent fuel is removed or not, the fission traveling wave advances toward the element in any given axial direction of the actinide “fuel” and converts it into the fission product “ash” Sometimes the loaded fuel allows higher density actinides to be replaced by lower density fission products without arbitrarily changing the entire volume of fuel elements.

As shown schematically, the progression of a fission traveling wave to a ²³² Th or ²³⁸ U charge fuel is enriched for a fissionable isotope (eg, without limitation, a fissionable isotope). A fission fuel assembly). An exemplary fission ignition module and method of propagating a fission traveling wave is described in US patent application Ser. No. 12 / 069,908, filed on Feb. 28, 2008, the contents of which are incorporated herein by reference. Inventors: Charles E. Ahlfeld, John Rogers Gilleland, Roderick A. Hyde, Muriel Y. Ishikawa, David G. McAlees, Nathan P. Myhrvold, Charles WHITMER, and Lowell L. Wood, Jr., Name: Nuclear Fission Igniter) In detail. Higher enrichment can produce smaller modules, and modules with minimal mass can employ moderator concentration gradients. Furthermore, the design of a fission ignition module can be determined in part by non-technical considerations (eg, prevention against diversion of material for military purposes in various situations).

  In other approaches, an exemplary fission igniter may have other types of reactivity feedstock. For example, other fission igniters are known as “burning ember” (eg, fission fuel that is enriched for fissionable isotopes via a neutron exposure in a propagating fission traveling wave reactor). ). Such “burning embers” can function as fission igniters regardless of the presence of various amounts of the fission product “ash”. In another approach for propagating a fission traveling wave, a fission ignition module enriched for fissionable isotopes is an electrically driven source of high energy ions (eg, protons, deuterons or alpha particles) Can be used to supplement other neutron sources that use, or electrons that can in turn generate neutrons. In one illustrative approach, a particle accelerator (eg, a linear accelerator) can be arranged to provide high energy protons for such intermediate materials that can in turn provide neutrons (eg, via fracturing). In other illustrative approaches, particle accelerators (eg, linear accelerators) are high relative to such intermediate materials that can in turn provide neutrons (eg, by electron splitting and / or photo splitting of high Z elements). Can be arranged to give energetic electrons. Alternatively, other known neutron radioactive processes and structures (eg, electrically induced fission techniques) are thereby enriched for fission isotopes to initiate the progression of fission waves. In addition to the module, it can provide neutrons that can be used (14 MeV neutrons from DT fusion).

As nuclear engineering of loaded fuels and fission traveling waves is described, further details on "fission ignition" and maintenance of fission traveling waves are described. A centrally located exemplary fission igniter that is reasonably enriched for fissile material (eg, ²³⁵ U or ²³⁹ Pu) (eg, electrical heating or one or more commanded by the operator) Having a neutron absorber (such as borohydride) that is removed from the igniter (by removal of the control rod), the fission igniter reaches neutron criticality. The local fuel temperature rises to a predetermined temperature and is subsequently controlled, for example by a reactor cooling system and / or a reactivity control system or a local temperature control module (the contents of which are hereby incorporated by reference). US patent application Ser. No. 11 / 605,943 (filing date: November 28, 2006, inventors: Roderick A. Hyde, Muriel Y. Ishikawa, Nathan P. Myhrvold, and Lowell L. Wood, Jr. , Name: AUTOMATED NUCLEAR POWER REACTOR FOR LONG-TERM OPERATION). Neutrons resulting from fast splitting of ²³³ U or ²³⁹ Pu are mostly captured by local ²³⁸ U or ²³² Th in the early stages.

  Fission igniter uranium enrichment is achieved by introducing a radial density gradient of a heat-resistant moderator (eg, graphite) into the nuclear fission igniter and fuel region that directly surrounds it, and a light water reactor (LWR). It is properly understood that the fuel level can be reduced to a level that does not significantly exceed the current fuel level. The high density of the moderator can sufficiently burn the low-enriched fuel, and the reduced density of the moderator can cause efficient splitting growth. Therefore, the optimal design of a fission igniter is a trade-off between the initial criticality, the shortest latency to availability of the full rated power resulting from the core's fully ignited charged fuel, and the robustness of growth. Can be related. The lower enrichment of the fission igniter entails the generation of a greater proliferative effect and thus imposes a longer waiting time.

  In some embodiments, the total storage of fissionable isotopes is increased, but the total storage is more spatially dispersed, so the peak reactivity of the core assembly is the first of the fission ignition processes. It will decline gradually in the period. As a result of the choice of initial fuel shape, fuel enrichment versus position, and fuel density, it can be set for maximum reactivity that the minimum is achieved when the minimum is achieved. Immediately thereafter, the maximum reactivity rapidly increases towards its maximum value, corresponding to the storage of fissionable isotopes in the region where significant excess isotopes remaining in the fission igniter are grown. start. For many cases, an approximately circular annular shell will then result in maximal output generation. At this point, the core assembly charge fuel may be referred to as “ignited”.

  The propagation of fission traveling waves (which may also be referred to herein as “fission combustion”) will now be described. In the configurations described so far, the circular shell of maximum local nuclear energy generation continues to progress radially from the fission igniter toward the outer surface of the loaded fuel. When the shell reaches the outer surface, the shell generally divides into two circular area surfaces, each of which propagates along one of the two opposite directions along the cylinder axis. At this point, the core potential of generating sufficient thermal energy is being demonstrated. This interval is characterized as the exit period of the two combustion wave fronts of the traveling fission wave reactor propagating in the axial direction. In some embodiments, the core loaded fuel center is ignited, thus generating two waves that propagate in opposite directions. This configuration doubles the core mass and volume at which power generation occurs at any given point in time, thus reducing the peak core specific power generation by a factor of two, thereby reducing heat transport issues. Minimize quantitatively. However, in other embodiments, the core charge fuel is ignited at or near one end as desired for a particular application. Such an approach can produce a single wave that propagates in some configurations.

  In other embodiments, the core charge fuel may be ignited at multiple sites. In still other embodiments, the core charge fuel is ignited at any 3D location within the core as desired for a particular application. In some embodiments, two propagating fission traveling waves can be evoked and propagate away from the fission ignition site. However, depending on the shape, composition of the fission fuel, the action of the control structure that regulates the neutrons, or other considerations, different numbers of fission traveling waves (eg, 1, 2, or 3) can be induced and propagated. However, for the sake of understanding and simplicity, the discussion herein refers to the propagation of the two combustion wave fronts of the fission traveling wave.

  From this time, when they reach or approach two opposite ends, proceed through two wave bursts, the physical process of nuclear energy generation is substantially time-dependent at either wave contour. Is stationary. The velocity of the wave traveling through the fuel is proportional to the local neutron flux that is linearly dependent on the heat output extracted from the core assembly via collective action on the neutron usage of the fission traveling wave in the neutron control system . In one approach, a neutron control system is disclosed in US patent application Ser. No. 11 / 605,933 (filing date: November 28, 2006, inventor: Roderick A. Hyde, the contents of which are incorporated herein by reference. , Muriel Y. Ishikawa, Nathan P. Myhrvold, and Lowell L. Wood, Jr., name: CONTROLLABLE LONG TERM OPERATION OF A NUCLEAR REACTOR). In other approaches, the neutron control system may be implemented using one or more rods containing neutron absorbers that are movable using one or more control rod drive means.

  In some embodiments, the temperature at the two ends of the core (in some embodiments), when greater power is needed from the reactor via a cooler coolant flowing into the core. , Closest to the coolant inlet) is slightly lower than the design setting of the temperature control module, which causes the neutron absorber to be extracted from the corresponding subpopulation of the core temperature control module. By means of this, the local neutron flux can be increased to bring about local thermal energy generation to a level that causes the local material temperature to reach the local temperature setting value. In some other embodiments, temperature control may be achieved by shimming the control rods as desired in response to the observed temperature change.

  In the two combustion wavefront embodiment, this process does not effectively heat the coolant until the coolant flow split in two is sufficiently transferred to the two nuclear combustion wavefronts. Then, these core loading fuels can generate significant levels of nuclear energy under conditions where the temperature of the fission fuel is not excessive (and regardless of the temperature at which the coolant reaches the core). The two parts serve to heat the coolant to a temperature specified by the design settings of those modules. The two streams of coolant then travel through two parts of the already burned fuel center of the two combustion wave fronts, removing the remaining fission and post-heat thermal energy from them, both at their centers Out of the loaded fuel. This configuration facilitates the propagation of the two combustion wavefronts toward the two ends of the loaded fuel, primarily by “removing” excess neutrons from the back of each wavefront.

Thus, the neutron engineering of the core in this configuration can be considered substantially self-regulated. For example, for a cylindrical core embodiment, the core neutronics is a cylindrical core density-radius fuel product greater than 200 gm / cm ² (ie, a composition typical for moderately fast neutron spectra). Can be considered substantially self-regulating if the average free path of 1-2 for fission in which neutrons are induced in the core of One of the functions of a neutron reactor in such a core design is that the outer part of the reactor (eg, its radiation shielding, structural support, outermost shell, and reactivity control elements (eg, limiting) Rather, it may substantially reduce the fast neutron fluence found near the control rod (if provided) or temperature control module (if provided))). Neutron reactors can also affect core performance by increasing the growth efficiency and specific power at the outermost part of the fuel. Such effects can increase the economic efficiency of the reactor. The portion away from the center of the loaded fuel is not used at the overall low energy efficiency, but has a level of isotope burnup comparable to that at the center of the loaded fuel.

  The neutron engineering of the core in the above configuration can be considered substantially self-regulating, and other configurations can operate under the control of the reactor control system. The reactor control system is equipped with a suitable electronic controller with suitable electronic circuitry and is movable using a suitable electromechanical system (eg, one or more drive mechanisms of control rods). One or more rods containing a neutron absorber).

Finally, the irreversible absence of core neutron reactivity can be achieved as desired at any time by injection of neutron poison into the coolant vapor. For example, using a material (eg, BF ₃ ), possibly accompanied by a volatile reducing agent (eg, H ₂ ), to impart a small amount of coolant vapor is otherwise a mild chemical reaction. Through exponential acceleration due to the high temperature at (2BF ₃ + 3H ₂ → 2B + 6H), the coolant tube passing through the core can be deposited substantially uniformly over the entire inner wall. Boron is a highly heat resistant metalloid and generally does not migrate from the deposited site. The substantially uniform presence of more than 100 kg of boron in the core can negate the neutron reactivity of the core for an infinitely long period without requiring the use of a powered mechanism in the vicinity of the reactor .

  In a general sense, those skilled in the art will recognize the various described herein that may be implemented individually and / or jointly by a wide range of hardware, software, firmware and / or any combination thereof. It is recognized that these aspects may be considered to constitute various “electrical circuits”. Thus, as used herein, an “electrical circuit” includes an electrical circuit having at least one separate electrical circuit, an electrical circuit having at least one integrated circuit, and at least one application. An electric circuit having a special integrated circuit, an electric circuit forming a general purpose arithmetic unit constituted by a computer program (eg a computer that at least partially performs processing and / or means) A general purpose computer configured by a program, or a microprocessor configured by a computer program that at least partially implements processing and / or means, a storage device (eg, a form of memory (eg, random access) , Flash, read-only, etc.)) Electrical circuit (e.g., a modem, communications switch devices, such as optoelectronic devices) that form an electrical circuit, and / or communication devices include, but are not limited to. Those skilled in the art will appreciate that the subject matter described herein can be implemented in an analog fashion, a digital fashion, or some combination thereof.

  In a general sense, those skilled in the art will recognize that the various embodiments described herein may be implemented individually and / or jointly by various types of electromechanical systems. . The system includes various electrical components (eg, hardware, software, firmware, and / or substantially any combination thereof); and various components that can provide mechanical force or operation (eg, , Rigid body, spring body or twisted body, hydraulic material, electromagnetically operated means, and / or substantially any combination thereof). Thus, as used herein, an “electromechanical system” includes an electrical circuit (eg, actuator, motor, piezoelectric crystal, micro electro mechanical system (MEMS)) that is operatively connected to a transducer. )), An electrical circuit having at least one separate electrical circuit, an electrical circuit having at least one integrated circuit, an electrical circuit having a special integrated circuit for at least one application, a computer An electrical circuit forming a general purpose computing device configured by the program (eg, a general purpose computer configured by a computer program that causes the processing and / or means to be performed at least in part, or By a computer program that causes the processing and / or means to be performed at least in part Microprocessors configured), storage circuits (eg, memory forms (eg, random access, flash, read-only, etc.)), electrical circuits forming communication devices (eg, modems) , Communication switching devices, optoelectric devices, etc.) and / or non-electrical analogues thereto (eg, optical analogues or other analogues). Those skilled in the art will also recognize that various electromechanical systems include various consumer electronics systems, medical devices, and other systems (eg, motor-driven transport systems, factory automated operating systems, security systems, and / or Appropriately understood, but not limited to, a communications / computing system).

(Exemplary embodiment)
An exemplary embodiment will now be described as a non-limiting example, since an overview has been given of the initiation and propagation of fission traveling waves.

  The following is a series of flowcharts depicting multiple implementations. For ease of understanding, the flowcharts are sub-component operations based on one or more previously represented flowcharts, with the first flowchart representing multiple implementations through an example implementation. Or, as any of the additional component actions, they are organized to represent alternative implementations and / or developments of the initial flowchart (s). Those skilled in the art will appreciate that the style of explanation utilized herein (eg, starting with the presentation of the flowchart (s) representing an example implementation and providing additional and / or further details in subsequent flowcharts). Appropriately understand that generally allows easy and quick understanding of various process implementations. Furthermore, those skilled in the art will appropriately further understand that the style of description used herein also adapts itself well to the design paradigm of modular and / or object-oriented programs.

  For purposes of overview and with reference now to FIG. 1A, an illustrative method 10 is shown for operating a fissioning traveling wave reactor. With further reference to FIG. 1B, an exemplary fission traveling wave core 12 of a fission traveling wave reactor is shown for purposes of illustration and not limitation. The fission fuel subassembly 14 is housed in the core assembly 16. To supplement clarity, FIG. 1B may illustrate fewer than all of the fission fuel subassemblies 14 that may be housed in an embodiment of the core assembly 16.

  A reference structure is defined within the reactor assembly 16. In some embodiments, the reference structure may be defined by x, y, and z dimensions. In some embodiments, the reference structure may be defined by a radial dimension and an axial dimension. In some embodiments, the reference structure may be defined by an axial dimension and a lateral dimension.

  In some embodiments, the fission fuel subassembly may be an individual fission fuel element (eg, a fission fuel rod, plate or sphere, etc.). In some embodiments, the fission fuel subassembly 14 may be a fission fuel assembly (ie, two or more individual fission fuel elements grouped into an assembly). Regardless of the embodiment of the fission fuel subassembly 14, the fission fuel material contained within the fission fuel subassembly 14 may be any suitable type of fission fuel material, as described above.

  As a further outline, the method 10 begins at block 18. At block 20, the combustion wave front of the fission traveling wave is directed along the first and second dimensions in the fission fuel subassembly 14 in the core assembly 16 of the fissioning traveling wave core 12 (as indicated by arrows 24). ) Propagated. At block 26, one of the fission fuel subassemblies 14 is selected to define the shape of the combustion wave front of the fission traveling wave along the second dimension according to the selected set of dimension restrictions. It is controllably moved along the first dimension from the first position to the second position. Method 10 stops at block 28.

  Illustrative details will now be described by way of non-limiting examples.

  The fission fuel subassembly 14 has a spatial relationship to the dimensions designated as the first dimension and the second dimension. For example, in some embodiments, the fission fuel assembly 14 may be elongated along the second dimension. In some embodiments, the second dimension can be the y dimension or the axial dimension. In some embodiments, the second dimension may be an x dimension, a z dimension, or a lateral dimension.

  Further, in some embodiments, the first dimension can be substantially orthogonal to the long axis of the fission subassembly 14. In some embodiments, the first dimension and the second dimension can be substantially orthogonal to each other.

  Various dimensions may be designated as the first dimension and the second dimension. For example, in some embodiments, the first dimension can include a radial dimension, and the second dimension can include an axial dimension. In some other embodiments, the first dimension can include an axial dimension, and the second dimension can include a radial dimension. In some embodiments, the first dimension can include an axial dimension, and the second dimension can include a lateral dimension. In some other embodiments, the first dimension can include a lateral dimension, and the second dimension can include an axial dimension. In a cylindrical core having an axially elongated assembly (eg, a typical configuration of an industrial light water reactor), the first dimension can be a radial dimension and the second dimension can be an axial dimension. possible. In other reactor configurations (eg, a CANDU heavy water reactor), the fuel assembly may be elongated in the first dimension and moved in the second dimension, either lateral or axial.

As illustrated in FIG. 1B, the position within the core 12 may be characterized as a first position and a second position according to various conditions. The location can generally be considered a space in the vicinity of the core around the fission fuel assembly 14. Also, the location can be generally considered to be a space that directly surrounds any given area in the core 12 or can be considered to be a large portion of the core 12. For example, with further reference to FIG. 1C in some embodiments, the first position can include the outer position 30 and the second position can include the inner position 32. As illustrated in FIG. 1C, in some embodiments, the inner location 32 and the outer location 30 may be based on a geometric approximation to the center of the core. In some other embodiments, the inner and outer positions may be based on neutron flux such that the neutron flux at the inner position is greater than the neutron flux at the outer position. In some embodiments, the inner and outer positions may be based on a reactivity such that the K _{effective at} the inner position is greater than the K _{effective at the} outer position. An exemplary embodiment of a traveling wave furnace may have an outer position that includes a position that is external to the propagating wave or a position toward the propagating wave, where the fission traveling wave is propagated, Or a position that has already propagated may be mentioned.

In some embodiments, with further reference to FIG. 1D for further illustration, the first position can include the inner position 32 and the second position can include the outer position 30. As illustrated in FIG. 1D, in some embodiments, the inner location 32 and the outer location 30 may be based on a geometric approximation to the central portion of the core 12. In some other embodiments, the inner and outer positions may be based on neutron flux such that the neutron flux at the inner position is greater than the neutron flux at the outer position. In some other embodiments, the inner position and the outer position may be based on a reactivity such that the K _{effective at} the inner position is greater than the K _{effective at the} outer position. In other embodiments, the inner and outer positions can be described in terms of the main nuclear reactions that occur in these regions. When considering a non-limiting example, the inner position can be mainly characterized by a fission reaction and the outer position can be mainly characterized by a nuclear absorption reaction with a material that can be converted to a fission material.

  Regardless of the characterization of the first position and the second position as either the inner position or the outer position, the first position and the second position can be characterized according to other attributes. For example, in some embodiments, the first position and the second position may be located on opposite sides of the reference value along the first dimension. In some other embodiments, the first location and the second location may include at least one attribute that is substantially equalized. For example, at least one attribute that is substantially equalized may include a geometric approximation to the central region of the core, neutron flux, or reactivity.

  Referring to FIG. 1E when considering a non-limiting example, one of the fission fuel subassemblies (not shown for clarity) is selected in the axial direction of the fission traveling wave combustion wavefront 22. It can be controllably moved radially outward from the inner position 32 toward the respective outer position 30 to define a shape according to a selected set of dimension constraints. For purposes of illustration and not limitation, changes in the shape of the combustion wavefront 22 of the fission traveling wave with respect to the axial direction are shown with radial movement of the fission fuel subassembly (not shown). The left pane illustrates the initial shape of the combustion wavefront 22 of the fission traveling wave. It is properly understood that only a quarter of the combustion wave front 22 of the fission traveling wave is shown for purposes of clarity.

  In the middle pane, the selected fission fuel subassembly (not shown) is selected according to the desired reactivity parameter (eg, burnup) or desired After being burned over time, it is moved radially from the inner position 32 to the outer position 30. The reactivity is moved radially outward from the radially positioned peak at the inner position 32 (shown in the left pane) to the outer position 30 (shown in the middle pane). Yes.

  Throughout the life of the fissioning traveling wave core 12, additional fission fuel subassemblies (not shown) can be moved radially outward from the inner location 32 to the outer location 30. As a result of such further outward movement, a fission fuel subassembly (not shown) in the radially inner position of the fissioning traveling wave core 12 will cause a fission fuel subassembly in the radially outer position of the fissioning traveling wave core 12. Greater combustion than the assembly can be maintained. As shown in the right pane, if a sufficient number of fission fuel subassemblies are moved radially outward as described above, then the shape of the combustion wave front 22 of the fission traveling wave becomes a Bessel function. Can be approximated. Also, if a sufficient number of fission fuel subassemblies in the fission traveling wave reactor 12 are moved radially outward as described above, then all or substantially all of the fission fuel subassemblies will be substantially simultaneously Each of the flammability limits can be reached or approached. In such cases, the use of fission fuel assemblies in the fissioning traveling wave core 12 is minimized.

  Referring to FIG. 1F for other non-limiting illustrations, of the fission fuel assembly 14 to define a shape according to a selected set of dimension restrictions in the axial direction of the combustion wavefront 22 of the fission traveling wave. Selected from each inner position 32 can be controllably moved radially outward from each inner position 32 toward each outer position 30, and one of the fission fuel assemblies 14 ′ selected can be It can be controllably moved radially inward from the outer position 30 towards the respective inner position 32. That is, the selected fission fuel assemblies 14 and 14 ′ are swapped between the inner position 32 and the outer position 30.

  For purposes of illustration and not limitation, an axial change of the fission traveling wave combustion wavefront 22 is shown with such radial movement of the fission fuel assemblies 14 and 14 'replaced. The left pane shows the initial shape of the combustion wavefront 22 of the fission traveling wave. In the left pane, the fission fuel assembly 14 has more fissile content than the fission fuel assembly 14 '. For example, the fission fuel subassembly 14 may be part of an ignition assembly for the fissioning traveling wave core 12. As another example, fission fuel assembly 14 is grown from a material that can be converted to fission material as a result of fast spectral neutron absorption and subsequent transmutation to fissionable isotopes in fissioning traveling wave core 12. May contain fissile material. In contrast, the fission fuel subassembly 14 ′ has less fissile content than the fission fuel subassembly 14. In some cases, the fission fuel subassembly 14 ′ has an isotope content that is convertible to more fission material than the fission fuel subassembly 14. In such a case, the fission fuel subassembly 14 ′ exhibits greater absorption for faster spectrum neutrons than the fission fuel subassembly 14.

  In the right pane, the selected fission fuel subassembly 14 has been moved radially outward from the inner position 32 to the outer position 30, and the selected fission fuel subassembly 14 ′ has been moved from the outer position 30 to the inner position. It has been moved radially inward to position 32. The axial profile of the combustion wave front 22 of the fission traveling wave after the replacement of the fission fuel subassemblies 14 and 14 'is the axial profile of the combustion wave front 22 of the fission traveling wave before such replacement (left pane). Is more dense and more uniform. In some embodiments, as a result, a substantially uniform profile or uniform profile may be achieved for the fission traveling wave combustion wavefront 22. In some other embodiments, it may not be desirable to achieve a substantially uniform profile or uniform profile for the fission traveling wave combustion wavefront 22. In such cases, it may only be desirable to rearrange the isotope material that can be converted to fissile material or fission material. In some other embodiments, it may be desirable to extend the fission traveling wave combustion wavefront 22 to a radial dimension.

  With further reference to FIG. 1G, the shape of the fission traveling wave combustion wavefront 22 can also be obtained by moving the fission fuel subassemblies 14 and 14 ′ in a radial dimension as described above with reference to FIG. 1f. Can be defined in the dimension. The radial profile of the fission traveling wave combustion wavefront 22 can be considered to represent the flow of neutron leakage. The left and right panes of FIG. 1G show views along the axial dimensions corresponding to the left and right panes of FIG. 1F, respectively.

  Referring now to FIG. 1H, one of the fission fuel subassemblies 14 selected to define a shape according to a selected set of dimension restrictions in the axial direction of the fission traveling wave combustion wavefront 22. It can be controllably moved in a lateral direction from each first position towards each second position.

The left pane shows the initial shape of the fission traveling wave combustion wavefront 22 viewed along the axial dimension. The selected fission fuel subassembly 14 is located at the first position z, r, ψ ₁ . In the example shown for purposes of illustration, the fission fuel subassembly 14 may be determined beyond any desired degree of reactivity at the first position z, r, ψ ₁ for any arbitrary reason. It contributes to the reactivity at 1 position z, r, ψ ₁ . For example, the fission fuel subassembly 14 may be part of an ignition assembly for the fissioning traveling wave core 12. As another example, fission fuel assembly 14 is grown from an isotope material that can be converted to fission material as a result of fast spectral neutron absorption and subsequent transmutation to fissionable isotopes in fissioning traveling wave core 12. May contain a fissile material. As a result, the combustion wavefront 22 of the fission traveling wave can propagate excessively in the radial direction of the first positions z, r, and ψ ₁ .

As shown in the right pane, the selected fission fuel subassembly is laterally along the lateral dimension ψ from the first position z, r, ψ ₁ to the second position z, r, ψ _2. It has been moved. The shape of the combustion wave front 22 of the fission traveling wave is as a result of the lateral movement of the selected fission fuel subassembly 14 from the first position z, r, ψ ₁ to the second position z, r, ψ ₂ . It is properly understood that it is defined in the radial direction. The lateral movement of the selected fission fuel subassembly 14 from the first position z, r, ψ ₁ to the second position z, r, ψ ₂ results in splitting from the first position z, r, ψ ₁ . The contents have been removed and splitting contents have been added to the second positions z, r, ψ ₁ . As shown in the right pane, the shape of the combustion wavefront 22 of the fission traveling wave is reduced along the radial dimension r in the vicinity of the first position z, r, ψ ₁ , and the second position z, It is enlarged along the radial dimension r in the vicinity of r and ψ ₂ .

  A controllable movement of a selected one of the fission fuel subassemblies 14 along a first dimension from a respective first position to a respective second position in block 26 is 1 It can involve more than one process. For example, with further reference to FIGS. 1I and 1J in some embodiments, selected from among the fission fuel subassemblies 14 along a first dimension from a respective first position toward a respective second position. Is controllably moved at block 26 to rotate at least one of the fission fuel subassemblies 14 at block 34, as indicated by arrow 36 (FIG. 1J). Can be included. Rotating at least one of the fission fuel subassemblies 14 in block 34 may suitably be performed using a fuel handling system in any suitable core as desired. Understood. Further, it may be desirable to rotate the selected fission fuel subassembly 14 to minimize or prevent reactor structural material deformation (eg, fuel rod bending of the fission fuel subassembly). .

  In some other embodiments, and with further reference to FIGS. 1K and 1L as another example, of the fission fuel subassemblies 14 along a first dimension from a respective first position toward a respective second position, Controllably moving in block 26 at least one selected from fission fuel subassemblies 14 is reversed in block 38 as indicated by arrow 40 (FIG. 1L). Can be included. Reversing at least one of the fission fuel subassemblies 14 in block 38 may suitably be performed using a fuel handling system in any suitable core as desired. Understood. Inverting the fission fuel subassembly 14 may cause the entrance of the fission fuel subassembly 14 (before inversion) to be the exit of the fission fuel subassembly 14 (after inversion) and vice versa. Such inversion may result in an axial thermal stress equalization at the end of the fission fuel subassembly 14 and / or an irradiation effect on the fission fuel subassembly 14. Any such irradiation effect can be a temperature associated with and / or associated with neutron flux variations at the axial end of the fissioning traveling wave core 12. It will be appreciated that the inversion of the fission fuel subassembly 14 occurs at both ends of the fission fuel subassembly 14 moving from the first position to the second position, which is inverted about the center point of the inversion. However, in some cases it may be desirable to change the lateral position of the assembly as well.

  It will also be appreciated that one or more optional dimensional constraints may be selected as desired for a particular application. For example, in some embodiments, the selected set of dimension restrictions may include a predetermined maximum distance along the second dimension.

  In some other embodiments, the selected set of dimension constraints may be a function of at least one combustion wavefront standard. For example, the combustion wavefront standard may include neutron flux. In some arrangements, the neutron flux may be associated with at least one selected from among the fission fuel subassemblies 14. In some other embodiments, the combustion wavefront standard may include neutron fluence. In some arrangements, the neutron fluence may be associated with at least one selected from among the fission fuel subassemblies 14.

  In some other embodiments, the combustion wavefront standard may include burnup. In some arrangements, the burnup may be associated with at least one selected from among the fission fuel subassemblies 14. In such an arrangement, a selected one of the fission fuel subassemblies 14 is moved from a first position having a first burnup rate to a second position having a second burnup rate. It may be desirable. If the selected fission fuel subassembly 14 is nearing the end of its useful life, then the first position may be a position characterized by a high burn-up rate and the second position is lowered. It may be a burnup rate (compared to a high burnup rate in the first position) or a location characterized by a substantially zero value burnup rate. In embodiments where the fission fuel subassembly 14 is to be propagated, it has a higher burnup rate (compared to the burnup rate of the first location) from the first location having a lower burnup rate. It may be desirable to move the fission fuel subassembly 14 to a second position.

  In some other embodiments, the combustion wavefront reference may include the location of the combustion wavefront that is within at least one of the fission fuel subassemblies 14 selected. The location of the combustion wavefront may be characterized by the characteristics of the fission traveling wave core 12 or the fission fuel subassembly 14 in them. Such properties can include, but are not limited to, mitotic rate, growth rate, power, temperature and reactivity.

  Controllably moving the fission fuel subassembly in block 26 along the first dimension from each first position toward each second position may be in any manner desired for a particular application. It will be appreciated that it can be implemented. For example, referring further to FIG. 1M (as shown in FIGS. 1C and 1D), in some embodiments, fission along the first dimension from each first location toward each second location. Controllably moving the fuel subassemblies at block 26 enables controllable fission fuel subassemblies at block 42 in a radial direction along a first dimension from a respective first position toward a respective second position. It can include moving. It will be appreciated that the radial movement in block 42 may be performed using a fuel handling system in any suitable core as desired.

  Still referring to FIGS. 1N and 1O in some other embodiments, the fission fuel subassembly is controllably moved in block 26 along a first dimension from a respective first position to a respective second position. The controllable movement of the fission fuel subassembly in block 44 spirals along the first dimension from the respective first position to the respective second position, as indicated by arrows 46. Can be included. It will be appreciated that the helical movement in block 44 may be implemented using a fuel handling system in any suitable core as desired.

  With further reference to FIGS. 1P and 1Q in some embodiments, controllably moving the fission fuel subassembly in block 26 along a first dimension from a respective first position toward a respective second position. Move controllably the fission fuel subassembly in block 44 axially along the first dimension from the respective first position toward the respective second position, as indicated by arrows 50. Can be included. It will be appreciated that the axial movement in block 48 may be performed using a fuel handling system in any suitable core as desired.

  The shape of the fission traveling wave combustion wavefront 22 may be any parameter associated with the fission traveling wave combustion wavefront 22 (eg, without limitation, neutron flux, neutron fluence, burnup and / or reactivity (or these). It is properly understood that any of the elements of It will also be appreciated that the fission traveling wave combustion wavefront 22 may have any shape as desired for a particular application. For example, with further reference to FIG. 1R in some embodiments, the shape of the fission traveling wave combustion wavefront 22 may be substantially spherical. Still referring to FIG. 1S in some other embodiments, the shape of the fission traveling wave combustion wavefront 22 may substantially match a selected surface that is continuously curved. Still referring to FIG. 1T in some embodiments, the shape of the combustion wavefront 22 of the fission traveling wave can be substantially rotationally symmetric about the second dimension. Still referring to FIGS. 1U and 1V in some other embodiments, the shape of the fission traveling wave combustion wavefront 22 may be substantially n-fold rotationally symmetric about the second dimension.

  A “flat” combustion profile (eg, a Bessel function) that is substantially constant throughout the core is likely to minimize the power that is maximized between the fission fuel subassemblies in the core and increase fuel utilization. Known by vendors. In the traveling wave fission reactor as described above, the combustion region of the reactor tends to increase in size due to a high conversion rate. The combustion zone is maintained at a high conversion rate with sufficient feed nuclear material (eg, isotope material or fissile material that can be converted to fission material).

  It will be appreciated that in some embodiments, there is the advantage of moving the fission fuel subassembly as described above to maintain the desired characteristics of the reactor combustion wavefront. For example, moving the fission fuel subassembly in the radial direction to the combustion region may serve to provide either the isotope material or the fissile material that can be converted to fission material to the reaction zone. Moving the fission fuel subassemblies radially outward may serve to move the fission fuel subassemblies that have reached the burnup limit out of the high neutron reactivity region. Also, the radially outward movement can help to reduce the power density of the combustion region by pre-diffusing the combustible fissionable fission fuel material into the non-combustion region. It is well understood that radial movement combined with spiral movement allows a finer spatial separation of radial movement to be combined with azimuth movement to further shape the combustion wavefront. The It will be appreciated that in some cases, a fission fuel subassembly may be replaced (or replaced) with a fission fuel subassembly at another location. In such a case, the isotope material that can be converted to fission material can be exchanged from a blanket region that can be converted to fission material with fully burned material obtained from the combustion region of the reactor. In other cases, the fission fuel material may be exchanged from the position of the immediately adjacent core so that two or more fission fuel subassemblies swap positions.

  Still referring to FIG. 1W in some embodiments, the shape along the second dimension of the fission traveling wave combustion wavefront 22 may be asymmetric. In some arrangements, the shape of the fission traveling wave combustion wavefront 22 may be rotationally asymmetric about the second dimension.

  Still referring to FIG. 1X in some embodiments, the method 20 includes using a fission traveling wave ignition assembly (not shown) to cause a fission traveling wave combustion wavefront 22 to be caused at block 52. Can do. An illustrative example of the initiation of a fission traveling wave combustion wavefront 22 using a fission traveling wave ignition assembly has been described above and need not be repeated. Still referring to FIG. 1Y, at block 54, at least one of the fission traveling wave ignition assemblies is moved along a first dimension from a respective first position to a respective second position of the fission fuel subassembly. Prior to controllably moving what is selected from them, it can be removed. In some embodiments, with further reference to FIG. 1Z, controllable one of the fission fuel subassemblies can be controlled along a first dimension from a respective first position to a respective second position. Prior to movement, removing at least one of the fission traveling wave ignition assemblies at block 54 includes a fission fuel subassembly assembly along a first dimension from a respective first position toward a respective second position. Removing at least one of the fission traveling wave ignition assemblies from a second position prior to controllably moving one of them selected may be included in block 56.

  Still referring to FIG. 1AA in some embodiments, a fissioning traveling wave reactor is selected from among the fission fuel subassemblies along a first dimension from a respective first position toward a respective second position. Before something is controllably moved, it is made subcritical in block 58. For example, referring further to FIG. 1AB in some embodiments, bringing the fissioning traveling wave reactor below subcritical at block 58 may include inserting a neutron absorber into the core at block 60.

  Still referring to FIG. 1AC in some embodiments, at block 62, a criticality is selected from among the fission fuel subassemblies along a first dimension from a respective first position toward a respective second position. It can be recovered after moving something controllably. For example, with further reference to FIG. 1AD in some embodiments, restoring criticality at block 62 may include removing at least a portion of the neutron absorber from the core at block 64.

  Still referring to FIG. 1AE in some embodiments, a fissioning traveling wave reactor is selected from among the fission fuel subassemblies along a first dimension from a respective first position toward a respective second position. Before things are controllably moved, they can be stopped at block 66. Still referring to FIG. AF, the fission traveling wave reactors controllably move a selected one of the fission fuel subassemblies along a first dimension from a respective first position toward a respective second position. After doing so, it can be restarted at block 68.

  2A and 1B, an exemplary method 200 is provided for controlling a fission traveling wave reactor in which a fission traveling wave combustion wavefront 22 is propagated along a first dimension and a second dimension. . Method 200 begins at block 202. At block 204, the desired shape of the fission traveling wave combustion wavefront 22 is determined along the second dimension in the fission fuel subassembly 14 according to the selected set of dimension restrictions. At block 206, the movement of one of the fission fuel subassemblies 14 selected is determined in a manner depending on the desired shape along the first dimension from the respective first position toward the respective second position. The

  With further reference to FIG. 2B in some embodiments, it will be appreciated that the current shape of the fission traveling wave combustion wavefront 22 is determined at block 210. The determination of the current shape of the fission traveling wave combustion wavefront 22 at block 210 is performed as desired in connection with determining the desired shape of the fission traveling wave combustion wavefront 22 at block 204. obtain. In some embodiments, the current shape of the fission traveling wave combustion wavefront 22 is determined at block 210 may be performed prior to determining the desired shape of the fission traveling wave combustion wavefront 22 at block 204. . In some other embodiments, determining the current shape of the fission traveling wave combustion wavefront 22 at block 210 is substantially equivalent to determining the desired shape of the fission traveling wave combustion wavefront 22 at block 204. Simultaneously. In some other embodiments, the current shape of the fission traveling wave combustion wavefront 22 is determined at block 210 after the desired shape of the fission traveling wave combustion wavefront 22 is determined at block 204. obtain. The desired shape is determined as desired (burn rate, estimated burn-up rate, growth rate, temperature distribution, power distribution, assembly operating history, and amount of reactivity of the fission fuel material moved within each location. Can be made).

  The fission fuel subassembly 14 may be selected for any purpose (e.g., building a desired shape of the fission traveling wave combustion wavefront 22 and / or fission traveling wave as desired for a particular application). It will be appreciated that the combustion wavefront 22 can be moved to maintain the desired shape). For example, with further reference to FIG. 2C in some embodiments, the movement of one selected from the fission fuel subassemblies 14 along a first dimension from a respective first position to a respective second position, In block 206, determining in a manner depending on the desired shape is to move selected ones of the fission fuel subassemblies 14 along a first dimension from each first position to each second position. May be determined at block 212 in a manner to build the desired shape. Still referring to FIG. 2D in some other embodiments, the movement of one selected from the fission fuel subassemblies 14 along a first dimension from a respective first position to a respective second position, Determining in a manner depending on the desired shape includes moving a selected one of the fission fuel subassemblies 14 along a first dimension from each first position to each second position, block 214. In a manner to maintain the desired shape.

  It will be appreciated that it is particularly preferable to determine when to perform the desired movement. In some embodiments and with reference to FIG. 2E for this purpose, the determination in block 216 includes the determination of the fission fuel subassembly 14 along a first dimension from the respective first position toward the respective second position. This is done according to the point in time when the one selected from them is moved in a manner depending on the desired shape. It will also be appreciated that the determination in block 216 may be made at any point in the performance of method 200 as desired.

  In some embodiments, selected ones of the fission fuel subassemblies 14 can be moved. Still referring to FIG. 2F, at block 218, one of the fission fuel subassemblies 14 is selected from a respective first position toward a respective second position in a desired shape along a first dimension. It can be moved in a corresponding manner.

  It will be appreciated that some aspects of method 200 are similar to some of the aspects of method 10 described above. These similar aspects are set forth for brevity, but these details need not be described for purposes of understanding.

  For example, referring further to FIG. 1B in some embodiments, the fission fuel subassembly 14 may be elongated along the second dimension. The first dimension can be substantially orthogonal to the elongate axis of the fission subassembly 14. The first dimension and the second dimension can be substantially orthogonal to each other.

  Still referring to FIG. 1B in a further example, the first dimension may include a radial dimension and the second dimension may include an axial dimension. In some other embodiments, the first dimension can include an axial dimension, and the second dimension can include a radial dimension. Any type of fission reactor may include a nuclear fission fuel subassembly extending across an axial dimension with a plurality of fission fuel subassemblies extending across a radial dimension. The fission traveling wave is axial in this case at a velocity different from the radial dimension, depending on the power distribution and divergence of the fission traveling wave (in particular in the configuration of the cylindrical core) from the inner region to the outer region. Can propagate along the dimensions of In this case, it is desirable to perform a radial movement of the fission fuel subassembly to maintain the waveform and characteristics in the axial dimension. For example, the propagation of fission traveling waves to the axial extent of the reactor region promotes neutron leakage from the core at the axial end of the core. Such a leak as described above reduces the conversion that makes the fissile material convertible into fissionable material in the fission reactor. A fission fuel subassembly having a combustion wavefront that is spread relative to an undesired axial position is a fission fuel subassembly that allows the fission fuel subassembly to reduce or limit further propagation of the combustion wavefront to undesired positions. It can be moved in a radial direction so that neutron reactivity at locations within the assembly is allowed. In other cases, based on the propagation of fission traveling waves in the axial dimension so that fissile material grown in the axial region of the fission fuel subassembly can be used elsewhere in the fission core. It may be desirable to move the fission fuel subassembly radially. At a given axial position, the combustion wavefront is made non-uniform in the radial dimension through controlled movement of the fission fuel subassembly so that different enrichment regions can be created, if desired. obtain. Placing a high enrichment region adjacent to a depleted enrichment region or a low enrichment region increases neutron leakage for low enrichment from the high enrichment region, thereby isolating isotopic material that can be converted to fission material. , Facilitating conversion to fissile material. It will be appreciated that the above movement can be implemented to facilitate propagation in the first dimension and to limit propagation in the second dimension.

  Still referring to FIG. 1B in some further examples, the first dimension may include an axial dimension and the second dimension may include a lateral dimension. In other examples, the first dimension may include a lateral dimension, and the second dimension may include an axial dimension.

Still referring to FIG. 1C as described above, the first position may include the outer position 30 and the second position may include the inner position 32. Also as described above, the inner position 32 and the outer position 30 may be based on a geometric approximation to the central portion of the core 12. Also, the inner position 32 and the outer position 30 may be based on neutron flux such that the neutron flux at the inner position 32 is greater than the neutron flux at the outer position 30. As described above, the inner position 32 and the outer position 30, _{K Effective} in the inner position 32 may be based on the larger such reactivity than _{K Effective} in the outer position 30.

Still referring to FIG. 1D in some embodiments, the first position can include the inner position 32 and the second position can include the outer position 30. The inner and outer positions are geometric approximations to the center of the core 12, neutron flux such that the neutron flux at the inner position is greater than the neutron flux at the outer position, and / or K _{effective at the} inner position is K at the outer position. _It can be based on a degree of reactivity that is greater than _effective .

  Referring to FIG. 1B in some embodiments, the first position and the second position may be located on opposite sides of the reference value of the reference value along the first dimension.

  Also, as shown in FIG. 1B in some embodiments, the first position and the second position may include at least one attribute that is substantially equalized. For example, the at least one attribute may include a geometric approximation to the central region of the core 12, neutron flux and / or reactivity.

  Still referring to FIG. 2G in some embodiments, the movement of a selected one of the fission fuel subassemblies along a first dimension from a respective first position to a respective second position at block 206. Determining may include determining at least one selected rotation of the fission fuel subassembly 14 at block 220. Still referring to FIG. 2H in some embodiments, the movement of a selected one of the fission fuel subassemblies along a first dimension from a respective first position to a respective second position at block 206. Determining may include determining at block 222 an inversion of at least one selected of the fission fuel subassemblies 14.

  In some embodiments, the selected set of dimension constraints may include a predetermined maximum distance along the second dimension. In some embodiments, the selected set of dimension constraints is a function of at least one combustion wavefront criterion. For example, the combustion wavefront reference may include a neutron flux (eg, without limitation, a neutron flux associated with at least one selected fission fuel subassembly 14). As another example, the combustion wavefront reference may include a neutron fluence (eg, without limitation, a neutron fluence associated with at least one selected fission fuel subassembly 14). As another example, the combustion wavefront criterion may include reactivity (eg, without limitation, reactivity associated with at least one selected fission fuel subassembly 14). As another example, the combustion wavefront criterion may include a burnup (eg, without limitation, a burnup associated with at least one selected fission fuel subassembly 14). In some embodiments, the combustion wavefront reference may include the location of the combustion wavefront within at least one selected fission fuel subassembly 14.

  Still referring to FIG. 2I in some embodiments, the movement of one of the selected fission fuel subassemblies 14 along a first dimension from a respective first position to a respective second position is shown at block 206. Determining at block 224 a radial movement of one of the selected fission fuel subassemblies 14 along a first dimension from a respective first position to a respective second position. Can be included. Still referring to FIG. 2J in some embodiments, the movement of one of the selected fission fuel subassemblies 14 along a first dimension from a respective first position to a respective second position is shown in block 206. Determining at may include determining, at block 226, a helical movement of one of the fission fuel subassemblies 14 selected. Still referring to FIG. 2K in some other embodiments, the movement of one selected from the fission fuel subassemblies 14 along a first dimension from a respective first position to a respective second position, Determining at block 206 may include determining an axial translation of one of the fission fuel subassemblies 14 selected at block 228.

  With further reference to FIG. 2L in some embodiments, determining the desired shape of the fission traveling wave combustion wavefront 22 at block 204 may result in the block 230 having a substantially spherical shape of the fission traveling wave combustion wavefront 22. Can be included. Still referring to FIG. 2M in some other embodiments, determining the desired shape of the fission traveling wave combustion wavefront 22 at block 204 along the second dimension is a continuation of the fission traveling wave combustion wavefront 22. Determining the shape of the curved surface at block 232. In some other embodiments, the curved surface can be formed such that the area of the surface of the combustion wavefront is promoted. In such embodiments, neutron leakage from the combustion zone to the breeding zone may be facilitated.

  The desired shape of the fission traveling wave combustion wavefront 22 can be any shape. As described above, in various embodiments, the desired shape of the fission traveling wave combustion wavefront 22 may be substantially rotationally symmetric about the second dimension; the desired fission traveling wave combustion wavefront 22 is desired. May be substantially n-fold rotationally symmetric about the second dimension; the desired shape of the fission traveling wave combustion wavefront 22 may be asymmetric; and / or the combustion wavefront of the fission traveling wave The 22 desired shapes can be rotationally asymmetric about the second dimension. In some other embodiments, n-fold symmetric symmetrical shapes can be converted into separate combustion compartments in a fissioning traveling wave core. For example, the combustion wavefront can be converted into round protrusions that can be further propagated to n or fewer (ie, neutronically separated) combustion regions (see FIG. 1V).

  Some embodiments may be provided as an exemplary system. For example, referring now to FIG. 3A, an exemplary system 300 is provided for determining movement of the fission fuel subassembly (not shown in FIG. 3A). Considering a non-limiting example, system 300 may provide a suitable system environment for implementation of method 200 (FIGS. 2A-2M). Still referring to FIG. 1B in some embodiments, because of the fission traveling wave combustion wavefront 22 propagating along the first and second dimensions, the electrical circuit 302 is responsible for fission progress within the fission fuel subassembly 14. The wave combustion wavefront 22 is configured to determine a desired shape along the second dimension according to a selected set of dimension restrictions. The electrical circuit 304 determines the movement of the selected one of the fission fuel subassemblies 14 along a first dimension from each first position to each second position in a manner depending on the desired shape. Is configured for.

  In a general sense, those skilled in the art will appreciate that the various aspects described herein may be implemented individually and / or jointly by various hardware, software, firmware and / or any combination thereof. Recognize that it can be considered to constitute a kind of “electrical circuit”. Thus, as used herein, an “electrical circuit” includes an electrical circuit having at least one separate electrical circuit, an electrical circuit having at least one integrated circuit, and at least one application. An electric circuit having a special integrated circuit, an electric circuit forming a general purpose arithmetic unit constituted by a computer program (eg a computer that at least partially performs processing and / or means) A general purpose computer configured by a program, or a microprocessor configured by a computer program that at least partially implements processing and / or means, a storage device (eg, a form of memory (eg, random access) , Flash, read-only, etc.)) Electrical circuit (e.g., a modem, communications switch devices, such as optoelectronic devices) that form an electrical circuit, and / or communication devices include, but are not limited to. Those skilled in the art will appreciate that the subject matter described herein can be implemented in a digital fashion or some combination thereof.

  Still referring to FIG. 3B in an illustrative example, electrical circuit 302 and / or electrical circuit 304 may be embodied as computing system 306 (which may also be referred to as a host computer or host system). In the illustrative embodiment, a central processing unit (“CPU”) (or microprocessor) 308 is connected to the system bus 310. A random access main memory (“RAM”) 312 is connected to the system bus 310 and is used to store data associated with one or more parameters of the storage device 314 (fission wave front 22 of the fission traveling wave). Access to the CPU 308. When executing the program instructions, CPU 308 stores those processing steps in RAM 312 and executes the stored processing steps from RAM 312.

  The computing system 306 may be connected to the computer network through a network connection (not shown) via the network interface 316. One such network is the Internet that enables computing system 306 to download applications, code, documents, and other electronic information.

  A read only memory (“ROM”) 318 is provided for storing an invariant instruction sequence (eg, a start instruction sequence or a basic input / output system (“BIOS”) sequence).

  An input / output (“I / O”) means interface 320 allows the computing system 306 to connect to various input / output means (eg, keyboard, pointing device (“mouse”), monitor, printer, modem, etc.). To do. The I / O means interface 320 is shown as a single block for simplicity and may include various interfaces for connecting with different types of I / O means.

  It will be appreciated that the embodiments are not limited to the construction of the computing system 306 shown in FIG. 3B. Depending on the application / business environment, computing system 306 may have several configurations. For example, the computing system 306 may be a set top box, laptop computer, laptop computer, desktop system, or other type of system.

  The portions of the system and method disclosed in various embodiments include a computer program product. Computer program products include computer readable recording media (eg, non-volatile recording media) and computer readable program code portions (eg, a series of computer instructions) embodied in a computer readable recording media. Can be mentioned. The computer program is typically recorded and executed by a processing device or associated memory means (eg, the processing elements depicted in FIG. 3B).

  In this regard, FIGS. 2A-2M and FIGS. 3A-3C are respective flowcharts and block diagrams of methods, systems and program products according to various embodiments. It is understood that each block in the flowcharts and block diagrams can be implemented by computer program instructions. These computer programs so that instructions executed on a computer or other programmable device generate means for performing the functions specified in the flowchart (s) or block diagram (s) The instructions may be loaded on a computer or other programmable device for generating a machine. In addition, instructions recorded in computer readable memory may cause a product (including means for performing the functions specified in the flowchart (s) or block diagram (s)) to be generated. These computer program instructions may be recorded in a computer readable memory that allows a computer or other programmable device to function in a particular fashion. A computer program instruction may also be used to produce a series of operational steps to be performed on a computer or other programmable device to produce processing performed on the computer or other programmable device. Load on a computer or other programmable device such that instructions executing on the other programmable device result in steps performing the functions specified in the flowchart (s) or block diagram (s) Can be done.

  Thus, a plurality of blocks in the flowchart or block diagram corresponds to a combination of means for performing the specified function, a combination of steps for performing the specified function, and a program instruction means for performing the specified function. doing. Also, each block of the flowchart or block diagram, and combinations of blocks in the flowchart or block diagram, may be a computer system based on a specific purpose hardware or a specific purpose hardware that performs the specified function or step. It is understood that it can be implemented by a combination of hardware and computer instructions.

  Still referring to FIG. 3C in some embodiments, the electrical circuit 304 may be further configured to determine the current shape of the fission traveling wave combustion wavefront 22. For example, the sensor 322 may be operatively connected to the electrical circuit 304 in communication via a suitable input interface 324. The sensor 322 may be any suitable sensor that measures parameters of the combustion wavefront 22 of the fission traveling wave. For example, sensor 322 may measure neutron flux, neutron fluence, burnup and / or reactivity (or any of those elements).

  Whether the computer program instructions are loaded on a computer or other programmable device for generating a machine so that the instructions executing on the computer or other programmable device generate a means for performing the function Regardless, as described above, embodiments of system 300 and electrical circuits 302 and 304 may be configured to provide a suitable system environment for implementation of method 200 (FIGS. 2A-2M). The function is a combination of specific purpose hardware and computer instructions, or a flowchart (s) implemented by a computer system based on specific purpose hardware that performs a specific function or step, block (s) Specific to each block in the figure, or flowchart or block diagram, and combinations of blocks in the flowchart (s) or block diagram. Several features of embodiments of the system 300 are described with further reference to FIGS. 1B-D, 1J, 1L, 1O, 1Q, 1R-1W, and 2A-2M.

  In response, in some embodiments, the electrical circuit 304 is moved from one of the fission fuel subassemblies 14 along a first dimension from a respective first position to a respective second position. Can be further configured to determine in a manner to build the desired shape. The electrical circuit 304 determines the movement of the selected one of the fission fuel subassemblies 14 along a first dimension from each first position to each second position in a manner that maintains the desired shape. In addition, it can be further configured. The electrical circuit 304 is responsive to a desired shape to move a selected one of the fission fuel subassemblies 14 along a first dimension from a respective first position toward a respective second position. It can be further configured to determine in a manner.

  As described above, in some embodiments, the fission fuel subassembly 14 may be elongated along the second dimension.

  Also, in some embodiments, as described above, the first dimension can be substantially orthogonal to the long axis of the fission fuel subassembly 14. In some other embodiments, the first dimension and the second dimension can be substantially orthogonal to each other.

  In various embodiments, the first dimension can include a radial dimension, the second dimension can include an axial dimension; the first dimension can include an axial dimension, The two dimensions may include a radial dimension; the first dimension may include an axial dimension, the second dimension may include a lateral dimension; and / or the first dimension May include a lateral dimension, and the second dimension may include an axial dimension.

In some embodiments, the first position can include the outer position 30 and the second position can include the inner position 32. The inner position 32 and the outer position 30 may have various desired properties (eg, without limitation, a geometrical approximation to the central portion of the core 12, the neutron flux at the inner position 32 is greater than the neutron flux at the outer position 30. And / or reactivity such that K _{effective at the} inner position 32 is greater than K _{effective at the} outer position 30).

In some other embodiments, the first position may include the inner position 32 and the second position may include the outer position 30. The inner position 32 and the outer position 30 may have various desired properties (eg, without limitation, a geometrical approximation to the central portion of the core 12, the neutron flux at the inner position 32 is greater than the neutron flux at the outer position 30. And / or reactivity such that K _{effective at the} inner position 32 is greater than K _{effective at the} outer position 30). In some embodiments, the first position and the second position may be located on opposite sides of the reference value along the first dimension.

  In some other embodiments, the first location and the second location may include at least one attribute that is substantially equalized. For example, the at least one attribute can include proximity to the central portion of the core 12, neutron flux and / or reactivity.

  In some embodiments, the electrical circuit 304 can be further configured to determine a selected at least one rotation of the fission fuel subassembly 14. In some other embodiments, the electrical circuit 304 may be further configured to determine a selected at least one inversion of the fission fuel subassembly 14.

  In some embodiments, as described above, the selected set of dimension restrictions may include a predetermined maximum distance along the second dimension.

  In some embodiments, the selected set of dimension restrictions may be a function of the combustion wavefront criterion. For example, the combustion wavefront criteria may include neutron flux (eg, a neutron flux associated with at least one selected fission fuel subassembly 14); neutron fluence (eg, at least one selected fission fuel subassembly 14) Associated neutron fluence); and / or burn-up (eg, burn-up associated with at least one selected fission fuel subassembly 14). In some embodiments, the combustion wavefront reference may include the location of the combustion wavefront within at least one selected interior of the fission fuel subassembly 14.

  In some embodiments, the electrical circuit 304 determines a radial movement of one selected from the fission fuel subassemblies 14 along a first dimension from each first position toward each second position. Can be further configured to. The electrical circuit 304 is further configured to determine a helical movement of a selected one of the fission fuel subassemblies 14 along a first dimension from each first position toward each second position. obtain. The electrical circuit 304 is further configured to determine an axial translation of a selected one of the fission fuel subassemblies 14 along a first dimension from a respective first position to a respective second position. Can be done.

  In some embodiments, the electrical circuit 302 may be further configured to determine a substantially spherical shape of the fission traveling wave combustion wavefront 22. The electrical circuit 302 can be further configured to determine the continuously curved shape of the combustion wavefront 22 of the fission traveling wave.

  In various embodiments, the desired shape of the fission traveling wave combustion wavefront 22 can be substantially rotationally symmetric about the second dimension; substantially n-fold rotationally symmetric about the second dimension. And / or asymmetric (eg, without limitation, by being rotationally asymmetric about the second dimension).

  Still referring to FIG. 4A as another example, another exemplary system 400 is provided for moving a fission fuel subassembly (not shown in FIG. 3A). As a non-limiting example, system 400 can provide a suitable system environment for implementation of method 100 (FIGS. 1A-1AF). Accordingly, the following discussion is made with further reference to FIGS.

  In some embodiments, for the fission traveling wave combustion wavefront 22 propagating along the first dimension and the second dimension, the electrical circuit 402 includes a fission traveling wave along the second dimension in the fission fuel subassembly 14. It is configured to determine the desired shape of the combustion wavefront 22 according to a selected set of dimensional constraints. The electrical circuit 404 is configured to determine the movement of one of the fission fuel subassemblies 14 along the first dimension in a manner that depends on the desired shape. Subassembly 405 is configured to move a selected one of fission fuel subassemblies 14 in response to electrical circuit 404.

  It will be appreciated that the electrical circuits 402 and 404 may be similar to the electrical circuits 302 and 304. In some cases, electrical circuits 402 and 404 may be the same as electrical circuits 302 and 304. Accordingly, for the sake of brevity, details need not be repeated for understanding.

  With further reference to FIG. 4B as a schematic, in the illustrative example, electrical circuit 402 and / or electrical circuit 404 may be embodied as a computer system 406 (also referred to as a host computer or host system). In the illustrative embodiment, a central processing unit (“CPU”) (or microprocessor) 408 is connected to the system bus 410. A random access main memory (“RAM”) is connected to the system bus 410 and is used by the CPU 408 to store data associated with one or more parameters of the storage device 414 (fission wave front 22 of the fission traveling wave). Get access to). When executing the program instructions, the CPU 408 stores these processing steps in the RAM 412 and executes the processing steps stored from the RAM 412. The computing system 406 may be connected to a computer network (not shown) through a network connection (not shown) via the network interface 416. A read only memory (“ROM”) is provided for storing a boot instruction sequence or a basic input / output system (“BIOS”) sequence). The input / output (“I / O”) means interface allows the computer system 406 to connect to various input / output means (eg, keyboard, pointing device (“mouse”), monitor, printer, modem, etc.). It will be appreciated that the embodiments are not limited to the structure of the computing system 406 shown in FIG. 4B. Also, a non-limiting discussion of computing system 306 applies to computing system 406.

  In various embodiments, portions of the disclosed system and method include one or more computer program products. Also, the above discussion of computer program products for system 300 (FIG. 3A) applies to system 400.

  In this regard, FIGS. 1A, 1I, 1K, 1M-1N, 1P, 1X-1AF, and 4A-4C are flowcharts and block diagrams that are respective flowcharts and block diagrams of methods, systems, and program products according to various embodiments. It will be appreciated that each block in and combinations of blocks in multiple flowcharts and block diagrams may be implemented by computer program instructions. These computer program instructions can be loaded. These computer programs so that instructions executed on a computer or other programmable device generate means for performing the functions specified in the flowchart (s) or block diagram (s) The instructions may be loaded on a computer or other programmable device for generating a machine. In addition, instructions recorded in computer readable memory may cause a product (including means for performing the functions specified in the flowchart (s) or block diagram (s)) to be generated. These computer program instructions may be recorded in a computer readable memory that allows a computer or other programmable device to function in a particular fashion. A computer program instruction may also be used to produce a series of operational steps to be performed on a computer or other programmable device to produce processing performed on the computer or other programmable device. Load on a computer or other programmable device such that instructions executing on the other programmable device result in steps performing the functions specified in the flowchart (s) or block diagram (s) Can be done.

  Thus, a plurality of blocks in the flowchart or block diagram corresponds to a combination of means for performing the specified function, a combination of steps for performing the specified function, and a program instruction means for performing the specified function. doing. Also, each block of the flowchart or block diagram, and combinations of blocks in the flowchart or block diagram, may be a computer system based on a specific purpose hardware or a specific purpose hardware that performs the specified function or step. It is understood that it can be implemented by a combination of hardware and computer instructions.

  With further reference to FIG. 4C in some embodiments, the electrical circuit 404 can be further configured to determine the current shape of the fission traveling wave combustion wavefront 22. For example, the sensor 422 can be operatively connected to the electrical circuit 404 in communication via a suitable input interface 424. The electrical circuit 404, sensor 422, and input interface 424 may be similar to the electrical circuit 304, sensor 322, and input interface 324 (FIG. 3C) (may be the same in some cases). Repeating these details is not essential for understanding.

  Whether the computer program instructions are loaded on a computer or other programmable device for generating a machine so that the instructions executing on the computer or other programmable device generate a means for performing the function Regardless, as described above, embodiments of system 400, electrical circuits 402 and 404, and subassembly 405 are of method 100 (FIGS. 1A, 1I, 1K, 1M-1N, 1P and 1X-1AF). It can be configured to provide a system environment suitable for implementation. The function is a combination of specific purpose hardware and computer instructions, or a flowchart (s) implemented by a computer system based on specific purpose hardware that performs a specific function or step, block (s) Specific to each block in the figure, or flowchart or block diagram, and combinations of blocks in the flowchart (s) or block diagram. Some features of the embodiment of the system 400 are described with further reference to FIGS.

  Referring to FIG. 4C in some embodiments, the electrical circuit 404 may be further configured to determine the current shape of the fission traveling wave combustion wavefront 22. Such a determination can be made in a similar manner or in the same manner by the electrical circuit 304 (FIG. 3A) as described above. In response, sensor 422 and input interface 424 are similar or in some cases the same as sensor 322 and input interface 324 (all in FIG. 3C). Sensor 422, input interface 424, and electrical circuit 404 cooperate as described above for sensor 322, input interface 324, and electrical circuit 304 (all in FIG. 3C).

  In some embodiments, the electrical circuit 404 may move the selected one of the fission fuel subassemblies 14 along a first dimension from a respective first position to a respective second position in a desired shape. Can be further configured to determine in a manner of constructing. The electrical circuit 404 determines the movement of the selected one of the fission fuel subassemblies 14 along a first dimension from each first position toward each second position in a manner that maintains the desired shape. In addition, it can be further configured.

  In some embodiments, the electrical circuit 404 is selected from among the fission fuel subassemblies 14 along a first dimension from a respective first position toward a respective second position. Can be further configured to determine when to move in a manner depending on the desired shape.

  In some embodiments, the fission fuel subassembly 14 may be elongated along the second dimension. The first dimension may be substantially orthogonal to the long axis of the fission fuel subassembly 14. The first dimension and the second dimension can be substantially orthogonal to each other.

  In various embodiments, the first dimension can include a radial dimension, the second dimension can include an axial dimension; the first dimension can include an axial dimension, The two dimensions may include a radial dimension; the first dimension may include an axial dimension, the second dimension may include a lateral dimension; and / or the first dimension May include a lateral dimension, and the second dimension may include an axial dimension.

In some embodiments, the first position can include the outer position 30 and the second position can include the inner position 32. The inner position 32 and the outer position 30 are geometrical approximations to the central portion of the core 12, a neutron flux such that the neutron flux at the inner position 32 is larger than the neutron flux at the outer position 30, and / or K _{effective at the} inner position 32. _May be based on a reactivity such that is greater than K _{effective at the} outer position 30.

In some other embodiments, the first position may include the inner position 32 and the second position may include the outer position 30. The inner position 32 and the outer position 30 are geometrical approximations to the central portion of the core 12, a neutron flux such that the neutron flux at the inner position 32 is larger than the neutron flux at the outer position 30, and / or K _{effective at the} inner position 32. _May be based on a reactivity such that is greater than K _{effective at} outer position 30.

  In some embodiments, the first position and the second position may be located on opposite sides of the reference value along the first dimension.

  In some other embodiments, the first location and the second location may include at least one attribute that is substantially equalized. For example, the at least one attribute can include proximity to the central portion of the core 12, neutron flux and / or reactivity.

  In some embodiments, the electrical circuit 404 can be further configured to determine a selected at least one rotation of the fission fuel subassembly 14. In some other embodiments, the electrical circuit 404 can be further configured to determine a selected at least one inversion of the fission fuel subassembly 14.

  Subassembly 405 includes any suitable nuclear fuel handling system known in the art (eg, without limitation, a fuel handling system in the core). However, in some other embodiments, the subassembly 405 may include an off-core fuel handling system.

  Regardless of the form in which the assembly 405 is embodied, in various embodiments, the assembly 405 may be selected from one of the fission fuel subassemblies 14 from a respective first position toward a second position. It may be further configured for radial movement. In various embodiments, the assembly 405 can be further configured to spirally select one of the fission fuel subassemblies 14 from a respective first position toward a second position. The assembly 405 can further be configured to axially move a selected one of the fission fuel subassemblies 14 from their respective first positions toward their respective second positions.

  In some embodiments, the assembly 405 may be further configured to rotate a selected one of the fission fuel subassemblies 14. In some other embodiments, the assembly 405 may be further configured to invert selected ones of the fission fuel subassemblies 14. Referring to FIG. 5 in various embodiments, an exemplary fission traveling wave reactor 500 can be provided. Examples of the fission traveling wave reactor 500 include a fission traveling wave core 12. As described above, the fission fuel subassembly 14 is housed in the fission traveling wave core 12. Each of the fission fuel subassemblies 12 is configured to propagate a combustion wavefront 22 of a fission traveling wave in them along the first and second dimensions. The electrical circuit 402 is configured to determine a desired shape along the second dimension of the fission traveling wave combustion wavefront 22 in the fission fuel subassembly 14 according to a selected set of dimension restrictions. . Although the electrical circuit 402 is selected from among the fission fuel subassemblies 14, it is configured to determine movement along the second dimension in a manner that depends on the desired shape. Subassembly 405 is configured to move selected one of fission fuel subassemblies 14 in response to electrical circuit 404.

  Accordingly, the reactor 500 can be embodied as the core 12 described above in cooperation with the system 400 in combination with the system 400 described above. Since details about the core 12 (and its components) and the system 400 (and its components) have been described above, details for understanding need not be repeated.

  In various embodiments, as described above, the electrical circuit 404 may be further configured to determine the current shape of the fission traveling wave combustion wavefront 22. The electrical circuit 404 is configured to move a selected one of the fission fuel subassemblies 14 along a first dimension from each first position to each second position in order to build a desired shape. It can be further configured to determine. The electrical circuit 404 moves the selected one of the fission fuel subassemblies 14 along a first dimension from each first position toward each second position in a manner to maintain a desired shape. It can be further configured to determine.

  As described above, in some embodiments, the electrical circuit 404 is selected from among the fission fuel subassemblies 14 along a first dimension from a respective first position toward a respective second position. Can be further configured to determine when to move in a manner depending on the desired shape.

  In some embodiments, the first dimension may extend along the second dimension.

  In some embodiments, the first dimension can be substantially orthogonal to the long axis of the fission fuel subassembly 14. In some embodiments, the first dimension and the second dimension can be substantially orthogonal to each other.

  In various embodiments, the first dimension can include a radial dimension, the second dimension can include an axial dimension; the first dimension can include an axial dimension, The two dimensions may include a radial dimension; the first dimension may include an axial dimension, the second dimension may include a lateral dimension; and / or the first dimension May include a lateral dimension, and the second dimension may include an axial dimension.

In some embodiments, the first position can include the outer position 30 and the second position can include the inner position 32. The inner position 32 and the outer position 30 are geometric approximations to the central portion of the core 12; the neutron flux such that the neutron flux at the inner position 32 is greater than the neutron flux at the outer position 30; and / or the K _{effective at the} inner position 32 is It may be based on a reactivity such as greater than K _{effective at the} outer position 30.

In some other embodiments, the first position may include the inner position 32 and the second position may include the outer position 30. The inner position 32 and the outer position 30 are geometric approximations to the central portion of the core 12; the neutron flux such that the neutron flux at the inner position 32 is greater than the neutron flux at the outer position 30; and / or the K _{effective at the} inner position 32 is It may be based on a reactivity such as greater than K _{effective at the} outer position 30.

  In some embodiments, the first position and the second position may be located on opposite sides of the reference value of the reference value along the first dimension.

  In some embodiments, the first location and the second location may include at least one attribute that is substantially equalized. The at least one attribute may include a geometric approximation to the central region of the core 12, neutron flux, and / or reactivity.

  In the various embodiments described above, the electrical circuit 404 is further configured to determine at least one rotation of one selected from the fission fuel subassembly 14 and / or further to the fission fuel subassembly 14. May be configured to determine at least one inversion of those selected from.

  In some embodiments, the selected set of dimensional constraints may include a predetermined maximum distance along the second dimension. In some other embodiments, the selected set of dimensional constraints include, but are not limited to, neutron flux (eg, neutron flux associated with at least one selected from the fission fuel subassembly 14), neutron fluence (Eg, a neutron fluence associated with at least one selected from the fission fuel subassembly 14), and / or a burnup (eg, a burnup associated with at least one selected from the fission fuel subassembly 14). Or a function of at least one combustion wavefront standard. In some embodiments, the combustion wavefront standard may include a combustion wavefront position within at least one selected from the fission fuel subassembly 14.

  In various embodiments, the electrical circuit 404 further determines a radial movement from a first position to a second position along a respective first dimension for a selection from the fission fuel subassembly 14. It may be configured. The electrical circuit 404 may further be configured to determine a helical movement from a first position to a second position along a respective first dimension for a selection from the fission fuel subassembly 14. The electrical circuit 404 may further be configured to determine axial translation for a selection from the fission fuel subassembly 14.

  In some embodiments, the electrical circuit 402 is further configured to determine a generally spherical shape of the fission progressive wave combustion wavefront 22 and / or a continuous curved shape of the fission progressive wave combustion wavefront 22. May be. The desired shape of the combustion wave front 22 of the fission traveling wave is substantially rotationally symmetric with respect to the second dimension, substantially n-fold rotationally symmetric with respect to the second dimension, and / or with respect to the second dimension. It may be asymmetric, such as rotationally asymmetric.

  In some embodiments, subassembly 405 may comprise a nuclear fuel handling device. As described above, subassembly 405 may comprise any suitable nuclear fuel handling device known in the art, such as, but not limited to, an in-core nuclear fuel handling device. However, in some embodiments, the subassembly 405 may include an out-of-core nuclear fuel handling device.

  In the above-described embodiments, the subassemblies 405 may be further configured to move each selected from the fission fuel subassembly 14 radially from the first position to the second position. The subassemblies 405 may further be configured to spirally move each selected from the fission fuel subassembly 14 from a first position to a second position. Subassembly 405 may further be configured to translate axially for a selection from fission fuel subassembly 14. Subassembly 405 may further be configured to rotate for a selection from fission fuel subassembly 14. Subassembly 405 may further be configured to invert for a selection from fission fuel subassembly 14.

  Referring now to FIG. 6A, in some embodiments, a traveling wave fission reactor operating method 600 is provided. The method 600 begins at block 602. Still referring to FIG. 1B, at block 604, at least one fission fuel assembly 14 is moved from a first position in the traveling wave fission reactor core 12 to a second position in the traveling wave fission reactor core 12. Moved outward. The method 600 ends at block 606.

  Still referring to FIG. 6B, in some embodiments, at block 608, at least one fission fuel assembly 14 may have been moved inwardly from the second position.

In some embodiments, the first position and the second position are, but not limited to, a geometric approximation to the central portion of the core 12; the neutron flux at the first position is greater than the neutron flux at the second position And a reactivity such that k _{effective at} the first position is larger than k _{effective at} the second position.

  Referring now to FIG. 7, in some embodiments, a traveling wave fission reactor operating method 700 is provided. The method 700 begins at block 702. Still referring to FIG. 1B, at block 704, at least one fission fuel assembly 14 is moved from a first position in the traveling wave fission reactor core 12 to a second position in the traveling wave fission reactor core 12. The movement in the first direction to is determined. The second position is different from the first position. At block 706, movement of the at least one fission fuel assembly 14 from the second position in the second direction is determined. The second direction is different from the first direction. The method 700 ends at block 708.

In some embodiments, the first direction may be an outer direction and the second direction may be an inner direction. The first position and the second position are, but not limited to, a geometric approximation to the center of the core 12; a neutron flux such that the neutron flux at the first position is greater than the neutron flux at the second position; and / or _{Alternatively,} it may be based on various attributes or parameters such as a degree of reactivity such that k _{effective at} the first position is larger than k _{effective at} the second position.

In some embodiments, the first direction may be an inner direction, and the second direction may be an outer direction. The second position and the first position are, but not limited to, a geometric approximation to the center of the core 12; a neutron flux such that the neutron flux at the second position is greater than the neutron flux at the first position; and / or _{Alternatively,} it may be based on various attributes or parameters such as a degree of reactivity that makes k _{effective at} the second position larger than k _{effective at} the first position.

  Referring now to FIG. 8, in some embodiments, a traveling wave fission reactor operating method 800 is provided. The method 800 begins at block 802. Still referring to FIG. 1B, at block 804, at least one fission fuel assembly 14 is moved from a first position in the traveling wave fission reactor core 12 to a second position in the traveling wave fission reactor core 12. To the first direction. The second position is different from the first position. At block 806, movement of the at least one fission fuel subassembly 14 from the second position in the second direction is determined. The second direction is different from the first direction. The method 800 ends at block 808.

In some embodiments, the first direction may be an outer direction and the second direction may be an inner direction. The first position and the second position are, but not limited to, a geometric approximation to the center of the core 12; a neutron flux such that the neutron flux at the first position is greater than the neutron flux at the second position; and / or _{Alternatively,} it may be based on various attributes or parameters such as a degree of reactivity such that k _{effective at} the first position is larger than k _{effective at} the second position.

In some embodiments, the first direction may be an inner direction, and the second direction may be an outer direction. The second position and the first position are, but not limited to, a geometric approximation to the center of the core 12; a neutron flux such that the neutron flux at the second position is greater than the neutron flux at the first position; and / or _{Alternatively,} it may be based on various attributes or parameters such as a degree of reactivity that makes k _{effective at} the second position larger than k _{effective at} the first position.

  Referring now to FIG. 9, in some embodiments, a traveling wave fission reactor operating method 900 is provided. The method 900 begins at block 902. Still referring to FIG. 1B, at block 904, at least one fission fuel assembly 14 is moved from a first position in the traveling wave fission reactor core 12 to a second position in the traveling wave fission reactor core 12. To the first direction. The second position is different from the first position. At block 902, at least one fission fuel assembly 14 is moved in the second direction from the second position. The second direction is different from the first direction. The method 900 ends at block 908.

In some embodiments, the first direction may be an outer direction and the second direction may be an inner direction. The first position and the second position are, but not limited to, a geometric approximation to the center of the core 12; a neutron flux such that the neutron flux at the first position is greater than the neutron flux at the second position; and / or _{Alternatively,} it may be based on various attributes or parameters such as a degree of reactivity such that k _{effective at} the first position is larger than k _{effective at} the second position.

In some embodiments, the first direction may be an inner direction, and the second direction may be an outer direction. The second position and the first position are, but not limited to, a geometric approximation to the center of the core 12; a neutron flux such that the neutron flux at the second position is greater than the neutron flux at the first position; and / or _{Alternatively,} it may be based on various attributes or parameters such as a degree of reactivity that makes k _{effective at} the second position larger than k _{effective at} the first position.

  Referring now to FIG. 10A, in some embodiments, a fission reactor operating method 1000 is provided. The method 1000 begins at block 1002. At block 1004, a predetermined burnup level is selected. At block 1006, for all of the plurality of fission fuel subassemblies, the movement of a selection from the plurality of fission fuel subassemblies within the core of the fission reactor is determined such that the burnup level is at the predetermined burnup level. Is done. The method 1000 ends at block 1008.

  Referring to FIG. 10B, in some embodiments, at block 1010, a selection from a plurality of fission fuel subassemblies within a nuclear fission reactor core is moved corresponding to the determined movement. Also good.

  Referring to FIG. 10C, in some embodiments, at block 1012, removal is for those selected from a plurality of fission fuel subassemblies when the burnup level is equal to the predetermined burnup level. , Each may be determined.

  Referring to FIG. 10D, in some embodiments, at block 1014, a selection from a plurality of fission fuel subassemblies may be removed in response to the determined removal.

  This application uses formal summary headings for clarity of display. However, throughout this application, the summary headings are for display purposes and various types of subject matter may be discussed (eg, the device / structure is described under the processing / operation headings and / or It will be understood that processing / operations are discussed under processing / operation headings and / or a single topic description may span two or more topic headings). From here on, the use of formal summary headings is not intended to be limiting.

  Those skilled in the art will now be taught elsewhere herein, as the specific exemplary processes and / or apparatus and / or techniques described above are in the claims appended hereto and / or elsewhere in the application. It will be understood that it is representative of more general processes and / or equipment and / or technology.

  Those skilled in the art will recognize that state-of-the-art technology has advanced and that there is little difference in processing hardware, software, and / or firmware system configurations. The use of hardware, software, and / or firmware is generally (but not necessarily, and in certain situations, the choice of hardware or software may be significant) and is cost-effective. It is a design item that is selected to make a compromise in effect. There are a variety of media (eg, hardware, software, and / or firmware) that can perform the processes and / or systems and / or other techniques shown in this disclosure, and preferred media are those processes and Those skilled in the art will appreciate that / or systems and / or other technologies will vary depending on the circumstances in which they are deployed. For example, if speed and accuracy are determined to be most important, mainly hardware and / or firmware media are selected, or if flexibility is determined to be most important, mainly software May be selected, or any combination of hardware, software, and / or firmware may be selected. Accordingly, there are a variety of media that can implement the processes and / or devices and / or other techniques shown in this disclosure, one is not inherently superior to the other, and all used. This medium is selected according to the situation in which the medium is deployed, and specific concerns (eg, speed, flexibility, or predictability) in implementation vary. Those skilled in the art will recognize that optically oriented hardware, software, and / or firmware are typically used when implementing optical configurations.

  In some implementations described herein, logic and similar processing may include software or other control structures. The electrical circuit may include, for example, one or more current paths configured and arranged to perform the various functions described herein. In some implementations, one or more of the media holds instructions that are detectable by the device when the medium is used to perform as described above, or that is detectable by the device when transmitted. May be configured to produce. In some variations, for example, the processing may be existing software or firmware, or gated array or programmable, by receiving or transmitting one or more instructions related to one or more operations described herein. May include hardware updates or changes. Alternatively, in some variations, processing may include special purpose hardware, software, firmware elements, and / or general purpose elements that process or invoke special purpose elements. Standards or other processing may be transmitted by passing through one or more of the specific transmission media described herein, packet transmissions as appropriate, or distributed media at various times.

  Alternatively, execution allows, triggers, collaborates, requires processing of a special purpose instruction sequence, or any one or more of the substantial functional operation events described herein. Alternatively, it may include invoking a circuit to produce. In some variations, the operational or logical description herein may be expressed as source code and compiled or invoked as an executable instruction sequence. In some situations, for example, processing may be provided in whole or in part by source code, such as C ++ or other code sequences. In other processes, source or other code processing may be compiled / processed / translated / converted into a high-level descriptor language using commercially available and / or conventional techniques (eg, initially C or C ++ programming). Written and processed in language technology, then programming language processing system, logic processing language processing system, hardware description language processing system, hardware design simulation processing system, and / or other expression modes similar to it To For example, some or all of the logical representation (eg, computer programming language processor) may be (eg, hardware description language (HDL) and / or very fast integrated circuit hardware description language (VHDL) or hardware (eg, application It may be manifested as a Verilog type hardware description (via other circuit models that may be used to form a physical process with a specific integrated circuit). Those skilled in the art will recognize how to obtain, configure and optimize optimal transmission or calculation elements, material supplies, actuators, or other structures in light of these teachings. .

  In the foregoing detailed description, various embodiments of the devices and / or processes have been described using block diagrams, flowcharts, and / or examples. Where these block diagrams, flowcharts, and / or embodiments include one or more functions and / or processes, each function and / or process in the block diagrams, flowcharts, or embodiments is applicable. Those skilled in the art will appreciate that a wide variety of hardware, software, firmware, or substantially any combination thereof can be implemented individually and / or in combination. In one embodiment, some of the components shown in this disclosure are implemented by an application specific integrated circuit (ASIC), a field programmable gate array (FPGA), a digital signal processor (DSP), or other integrated form. be able to. However, some forms of embodiments presented in this disclosure may be executed in whole or in part on one or more computer programs (eg, executed on one or more computer systems) executed on one or more computers. One or more programs), one or more programs executed on one or more processors (eg, one or more programs executing on one or more microprocessors), firmware, or substantially any of these Combinations can equally be implemented within an integrated circuit, and circuit design and / or writing of codes to the software and / or firmware is well within the scope of those skilled in the art. Those skilled in the art will recognize that. Further, the component mechanisms shown in this disclosure can be distributed in various forms as program products, and the component embodiments shown in this disclosure are the signals that are actually used to implement the distribution. Those skilled in the art will understand that this applies regardless of the type of media having Examples of media having signals include recording media (eg, floppy (registered trademark) disk, hard disk drive, compact disk (CD), digital video desk (DVD), digital tape, computer memory, etc.), and transmission type. Media (eg, digital and / or analog communication media (eg, fiber optic cables, waveguides, wired communication links, wireless communication links (eg, transmitters, receivers, transmit logic operations, receive logic operations, etc.)). However, it is not limited to these.

  In general terms, those skilled in the art will recognize that the various embodiments described herein are a wide range of electrical components (eg, hardware, software, firmware, and / or substantially any combination thereof), and A wide range of components that impart mechanical force or movement (eg, rigid bodies, springs (ie, torsional objects), hydraulic devices, devices driven by electromagnetism, and / or virtually any of these It will be appreciated that it can be performed individually and / or collectively by various electromechanical systems having a combination. As a result, as used herein, examples of “electromechanical systems” are operable with transducers (eg, actuators, motors, piezoelectric crystals, microelectromechanical systems (MEMS), etc.). Combined electrical circuit configuration, electrical circuit configuration having at least one discrete electrical circuit, electrical circuit configuration having at least one integrated circuit, electrical circuit configuration having at least one application specific integrated circuit, configured by a computer program An electrical circuit configuration that forms a general purpose computing device (eg, a general purpose computer configured by a computer program or at least partly implementing the process and / or device described herein, or the process and / or method described herein) Or at least partially implement the device A microprocessor configured by a computer program), an electric circuit configuration forming a memory device (for example, various forms of memory (eg, RAM, flash memory, ROM, etc.), an electric circuit configuration forming a communication device (for example, a modem, Communication switches, opto-electrical facilities, etc.) and / or any non-electrical equivalents thereof (eg optical equivalents or other equivalents), etc., but not limited to these examples Those of ordinary skill in the art may further include various household electrical systems, medical devices, and other systems (eg, motorized transport systems, factory manufacturing process automation systems) as examples of electromechanical systems. Security system, and / or communication / computation system) It will be understood that these examples are not intended to be limiting, and those skilled in the art will understand that an electromechanical device, as used herein, is an electrical It will be appreciated that the invention is not limited to systems having both drive and mechanical drive.

  All of the above US patents, US patent application publications, US patent applications, foreign patents, foreign patent applications, and non-patent publications referenced herein and / or listed in any application data sheet To the extent not inconsistent, incorporated herein by reference.

  Those skilled in the art will appreciate that the elements (eg, operations), devices, objects, and accompanying discussions described herein have been used as examples for purposes of conceptual clarification, and that various configuration modifications are contemplated. You will understand that. Thus, as used herein, the described examples and accompanying discussion are intended to be representative of a more general class. In general, the use of a particular example is intended to be representative of that class, and the absence of a particular element (eg, operation), device, and subject should not be considered limiting.

  For essentially any plural and / or singular terms herein, one of ordinary skill in the art will recognize the plural and singular and / or singular to plural as appropriate to the context and / or application. Can be translated into The various singular / plural permutations are not shown here for the sake of clarity.

  The subject matter described herein refers to different components that are sometimes contained within or connected to other different components. It will be appreciated that such a structure shown is merely an example, and that many other structures that actually accomplish the same function may be implemented. In a conceptual sense, any composition of a composition that accomplishes the same function is effectively “associated” so that the desired function is achieved. From here, any two components that are combined here to achieve a particular function are “related” to each other so that the desired function is achieved regardless of structure or intermediate components. Similarly, any two well-related components can also be “operably connected” or “operably coupled” to each other to achieve the desired function. Any two components that are well related can then be “operably coupleable” to each other to achieve the desired function. Examples of operably coupleable are not particularly limited, but may be physically paired and / or physically interacting components and / or wirelessly interactable and / or wirelessly interacting components and Components that interact and / or logically interact.

  While specific embodiments of the subject matter described herein have been illustrated and described, changes and modifications do not depart from the subject matter described herein and the broader aspects, and therefore, the appended claims are Those skilled in the art should understand, based on the teachings herein, that all changes and modifications are within the scope, and further within the true spirit and scope of the subject matter described herein. Those skilled in the art generally intend that the terms used herein, particularly those used in the appended claims (eg, in the appended claims text), are generally “open” terms. (For example, the term “including” should be construed as “including but not limited to”) Should be interpreted as "having at least ..." and the term "comprising ..." should be interpreted as "including but not limited to" ). Further, if a specific number of components introduced in a claim is intended, such intention is expressly stated in the claim, and such explicit description It will be understood by those skilled in the art that such intent does not exist in the absence of. As an aid to understanding, introductory expressions such as “at least one” or “one or more” may be used in the following appended claims to introduce claim elements. Absent. However, even if such an expression is used, the introduction of a claim component by the indefinite article “a” or “an” includes any component introduced in the claim. Should not be construed as implying that this particular claim is limited to claims containing only one such component. Similarly, such an interpretation may include the introductory expression “one or more” or “at least one” and an indefinite article, such as “a” or “an”, in the same claim. Again, this should not be done (eg, “a” and / or “an” should normally be taken to mean “at least one” or “one or more”). The same is true for the use of definite articles used to introduce claim elements. Further, even if the specific number of components introduced in the claims is explicitly stated, those skilled in the art usually include at least the stated number. It should be understood that it should be construed as meaning (for example, where “two components” is simply described without the use of a modifier, Means at least two or more). Further, when a similar expression format is used for “at least one of A, B, C, etc.”, generally such a sentence structure will be understood by those skilled in the art. Intended for meaning (eg, “a system having at least one of A, B, and C” includes a system having only A, a system having only B, a system having only C, and A and B). , A system having both A and C, a system having both B and C, and / or a system having both A, B, and C, etc., but are not limited to this). Where a similar form of expression is used for “at least one of A, B, C, etc.”, such a sentence structure generally has the meaning that would be understood by those skilled in the art. Intended (eg, “a system having at least one of A, B, or C” includes a system having only A, a system having only B, a system having only C, and A and B together. A system having both A and C, a system having both B and C, and / or a system having both A, B, and C, etc.). Moreover, those of ordinary skill in the art typically use disjunctive words and / or expressions to present more than one optional term either in the specification, in the claims, or in the drawings. As long as it is consistent with the context, it may contain one of the terms, one of the terms, or may contain both terms. It will be understood that it should be understood that it is considered. For example, the expression “A or B” is generally understood to include the possibility of being “A” or the possibility of being “B” or the possibility of being “A and B”.

  With respect to the appended claims, those skilled in the art will appreciate that the actions described in a claim may generally be performed in any order. Also, although the various operational flows are presented as a series of flows, it is understood that the various operations may be performed in other orders than the illustrated order, or may be performed simultaneously. It should be. Examples of such other sequences may include repetitive, alternating, interrupted, reordered, incremental, prepared, replenished, simultaneous, reverse, or other modified orders, as long as they are not inconsistent with the context. Good. Further, terms such as “corresponding to”, “related to”, or adjectives in past tense are not generally intended to exclude such variations unless otherwise specified. .

  The subject matter aspects described herein are listed below by number.

[1] propagating a fission traveling wave combustion wavefront along a first dimension and a second dimension within a plurality of fission fuel subassemblies in a traveling wave fission reactor core;
Each selected from the plurality of fission fuel subassemblies along the first dimension so as to define a combustion wavefront shape of the fission traveling wave along the second dimension based on a selected set of dimensional constraints. Moving in a controllable manner from the first position to the second position.

  [2] The method according to [1], wherein the plurality of fission fuel subassemblies extend along the second dimension.

  [3] The method according to [1], wherein the first dimension is substantially orthogonal to a major axis of the plurality of fission fuel subassemblies.

  [4] The method according to [1], wherein the first dimension and the second dimension are substantially perpendicular to each other.

[5] The method according to [1], wherein the first dimension includes a radial dimension, and the second dimension includes an axial dimension.

[6] The method according to [1], wherein the first dimension includes an axial dimension, and the second dimension includes a radial dimension.

[7] The method according to [1], wherein the first dimension includes an axial dimension, and the second dimension includes a lateral dimension.

[8] The method according to [1], wherein the first dimension includes a lateral dimension, and the second dimension includes an axial dimension.

[9] The method according to [1], wherein the first position includes an outer position, and the second position includes an inner position.

  [10] The method according to [9], wherein the inner position and the outer position are based on a geometric approximation with respect to a central portion of the reactor core.

  [11] The method according to [9], wherein the inner position and the outer position are based on a neutron flux such that the neutron flux at the inner position is larger than the neutron flux at the outer position.

[12] The method according to [9], wherein the inner position and the outer position are based on a reactivity such that k _{effective at} the inner position is larger than k _{effective at the} outer position.

[13] The method according to [1], wherein the first position includes an inner position, and the second position includes an outer position.

  [14] The method according to [13], wherein the inner position and the outer position are based on a geometric approximation with respect to a central portion of the reactor core.

  [15] The method according to [13], wherein the inner position and the outer position are based on a neutron flux such that the neutron flux at the inner position is larger than the neutron flux at the outer position.

[16] The method according to [13], wherein the inner position and the outer position are based on a reactivity such that k _{effective at} the inner position is larger than k _{effective at the} outer position.

  [17] The method according to [1], wherein the first position and the second position are located on opposite sides of the reference value along the first dimension.

  [18] The method of [1], wherein the first position and the second position include at least one attribute that is substantially equalized.

  [19] The method according to [18], wherein the at least one attribute includes a geometric approximation to a central region of the reactor core.

  [20] The method according to [18], wherein the at least one attribute includes a neutron flux.

  [21] The method according to [18], wherein the at least one attribute includes reactivity.

  [22] For the one selected from the plurality of fission fuel subassemblies, each of the plurality of fission fuel subassemblies is controllably moved along a first dimension from a first position to a second position. The method according to [1], comprising rotating at least one selected from the group consisting of:

  [23] For each selected one of the plurality of fission fuel subassemblies, each of the plurality of fission fuel subassemblies is controllably moved along a first dimension from a first position to a second position. The method according to [1], comprising inverting at least one selected from the group consisting of:

  [24] The method according to [1], wherein the dimension restriction of the selected set includes a predetermined maximum distance along the second dimension.

  [25] The method of [1], wherein the selected set of dimension limits is a function of at least one combustion wavefront standard.

  [26] The method according to [25], wherein the combustion wavefront standard includes a neutron flux.

  [27] The method of [26], wherein the neutron flux is associated with at least one selected from the plurality of fission fuel subassemblies.

  [28] The method according to [25], wherein the combustion wavefront standard includes neutron fluence.

  [29] The method of [28], wherein the neutron fluence is related to at least one selected from the plurality of fission fuel subassemblies.

  [30] The method according to [25], wherein the combustion wavefront standard includes a burnup degree.

  [31] The method of [30], wherein the burnup is related to at least one selected from the plurality of fission fuel subassemblies.

  [32] The method of [25], wherein the combustion wavefront standard includes a combustion wavefront position within at least one selected from the plurality of fission fuel subassemblies.

  [33] For each selected from the plurality of fission fuel subassemblies, each of the plurality of fission fuel subassemblies is controllably moved along a first dimension from a first position to a second position. The method according to [1], comprising controllably moving each selected from the first position to the second position in the radial direction along the first dimension.

  [34] For each selected one of the plurality of fission fuel subassemblies, each of the plurality of fission fuel subassemblies is controllably moved along a first dimension from a first position to a second position. The method according to [1], further comprising: controllably moving each selected from the first position to the second position spirally along the first dimension.

  [35] For each selected from the plurality of fission fuel subassemblies, each of the plurality of fission fuel subassemblies is controllably moved along a first dimension from a first position to a second position. The method according to [1], further comprising: controllably moving each selected from the first position to the second position along the first dimension in the axial direction.

  [36] The method according to [1], wherein a combustion wavefront shape of the fission traveling wave is a substantially spherical shape.

  [37] The method according to [1], wherein the combustion wavefront shape of the fission traveling wave substantially conforms to a selected continuous curved surface.

  [38] The method according to [1], wherein the combustion wavefront shape of the fission traveling wave is substantially rotationally symmetric with respect to the second dimension.

  [39] The method according to [1], wherein the combustion wavefront shape of the fission traveling wave is substantially n-fold rotationally symmetric with respect to the second dimension.

  [40] The method according to [1], wherein a combustion wavefront shape of the fission traveling wave along the second dimension is asymmetric.

  [41] The method according to [40], wherein the combustion wavefront shape of the fission traveling wave is rotationally asymmetric with respect to the second dimension.

  [42] The method of [1], further comprising generating a combustion wavefront of the fission traveling wave by a plurality of fission traveling wave ignition assemblies.

  [43] For a selection of the plurality of fission fuel subassemblies, each of the plurality of fission traveling wave ignitions before each controllably moves along the first dimension from the first position to the second position. The method of [42], wherein at least one of the assemblies is removed.

  [44] For a selection of the plurality of fission fuel subassemblies, a plurality of fission traveling wave ignition assemblies before each controllably moving along a first dimension from a first position to a second position Removing at least one of the plurality of fission fuel subassemblies selected from each of the plurality of fission fuel subassemblies controllably moves along a first dimension from a first position to a second position; Removing at least one of the plurality of fission traveling wave ignition assemblies from the second position.

  [45] The traveling wave fission reactor is further configured to controllably move each of the selected fission fuel subassemblies from the first position to the second position along the first dimension. The method according to [1], which comprises making the temperature less than critical.

  [46] The method according to [45], wherein making the traveling wave fission reactor less than critical includes introducing a neutron absorber into the core of the reactor.

  [47] Further, for each selected from the plurality of nuclear fission fuel subassemblies, each is controllably moved from the first position to the second position along the first dimension, and then recovered critically. [45] The method according to [45].

  [48] The method according to [47], wherein the recovery to criticality includes removing at least a neutron absorber portion from the core of the reactor.

  [49] The traveling wave fission reactor is further configured to controllably move each selected from the plurality of fission fuel subassemblies along the first dimension from the first position to the second position. [45] The method of [45] including stopping.

  [50] Further, the one selected from the plurality of nuclear fission fuel subassemblies is controllably moved from the first position to the second position along the first dimension, and then the traveling wave fission reactor The method according to [49], including restarting.

[51] Along the second dimension within a plurality of fission fuel subassemblies based on a selected set of dimensional constraints on the combustion wavefront of the fission traveling wave propagating along the first and second dimensions. Determining the desired shape of the combustion wave front of the traveling fission wave,
Determining a movement from a first position to a second position along a respective first dimension to correspond to the desired shape for a selection from the plurality of fission fuel subassemblies; and a traveling wave How to control a nuclear fission reactor.

  [52] The method according to [51], further comprising determining an existing shape of a combustion wavefront of the fission traveling wave.

  [53] Determining the movement from the first position to the second position along each first dimension for the selected one of the plurality of fission fuel subassemblies to correspond to the desired shape; Determining a movement from a first position to a second position along a respective first dimension for the selected one of the plurality of fission fuel subassemblies to build the desired shape. [51] The method of description.

  [54] Determining the movement from the first position to the second position along each first dimension for the selected one of the plurality of fission fuel subassemblies to correspond to the desired shape; Determining a movement from a first position to a second position along a respective first dimension for the selected one of the plurality of fission fuel subassemblies to maintain the desired shape. [51] The method of description.

  [55] Further, when the selected one of the plurality of nuclear fission fuel subassemblies is moved from the first position to the second position along the first dimension so as to correspond to the desired shape. The method according to [51], comprising:

  [56] Further, each selected from the plurality of nuclear fission fuel subassemblies is moved from the first position toward the second position along the first dimension so as to correspond to the desired shape. [51] The method according to [51].

  [57] The method according to [51], wherein the plurality of nuclear fission fuel subassemblies extend along the second dimension.

  [58] The method according to [51], wherein the first dimension is substantially orthogonal to a major axis of the plurality of fission fuel subassemblies.

  [59] The method according to [51], wherein the first dimension and the second dimension are substantially perpendicular to each other.

[60] The method according to [51], wherein the first dimension includes a radial dimension, and the second dimension includes an axial dimension.

[61] The method according to [51], wherein the first dimension includes an axial dimension, and the second dimension includes a radial dimension.

[62] The method according to [51], wherein the first dimension includes an axial dimension, and the second dimension includes a lateral dimension.

[63] The method according to [51], wherein the first dimension includes a lateral dimension, and the second dimension includes an axial dimension.

[64] The method according to [51], wherein the first position includes an outer position, and the second position includes an inner position.

  [65] The method according to [64], wherein the inner position and the outer position are based on a geometric approximation with respect to a central portion of the reactor core.

  [66] The method according to [64], wherein the inner position and the outer position are based on a neutron flux such that the neutron flux at the inner position is larger than the neutron flux at the outer position.

[67] The method according to [64], wherein the inner position and the outer position are based on a reactivity such that k _{effective at} the inner position is larger than k _{effective at the} outer position.

[68] The method according to [51], wherein the first position includes an inner position, and the second position includes an outer position.

  [69] The method according to [68], wherein the inner position and the outer position are based on a geometric approximation with respect to a central portion of the reactor core.

  [70] The method according to [68], wherein the inner position and the outer position are based on a neutron flux such that the neutron flux at the inner position is larger than the neutron flux at the outer position.

[71] The method according to [68], wherein the inner position and the outer position are based on a reactivity at which k _{effective at} the inner position is larger than k _{effective at the} outer position.

  [72] The method according to [51], wherein the first position and the second position are located on opposite sides of the reference value along the first dimension.

  [73] The method of [51], wherein the first position and the second position include at least one attribute that is substantially equalized.

  [74] The method of [73], wherein the at least one attribute includes a geometric approximation to a central region of the reactor core.

  [75] The method according to [73], wherein the at least one attribute includes a neutron flux.

  [76] The method according to [73], wherein the at least one attribute includes reactivity.

  [77] For a selection from the plurality of fission fuel subassemblies, determining the movement from a first position to a second position along a respective first dimension is selected from the plurality of fission fuel subassemblies The method according to [51], comprising: determining at least one rotation among those performed.

  [78] For one selected from the plurality of fission fuel subassemblies, determining the movement from a first position to a second position along a respective first dimension is selected from the plurality of fission fuel subassemblies. The method according to [51], comprising determining at least one inversion of the one performed.

  [79] The method of [51], wherein the selected set of dimension restrictions includes a predetermined maximum distance along the second dimension.

  [80] The method of [51], wherein the selected set of dimension limits is a function of at least one combustion wavefront standard.

  [81] The method according to [80], wherein the combustion wavefront standard includes a neutron flux.

  [82] The method of [81], wherein the neutron flux is associated with at least one selected from the plurality of fission fuel subassemblies.

  [83] The method according to [80], wherein the combustion wavefront standard includes a neutron fluence.

  [84] The method of [83], wherein the neutron fluence is related to at least one selected from the plurality of fission fuel subassemblies.

  [85] The method according to [80], wherein the combustion wavefront standard includes a burnup degree.

  [86] The method of [85], wherein the burnup is related to at least one selected from the plurality of fission fuel subassemblies.

  [87] The method of [80], wherein the combustion wavefront standard includes a combustion wavefront position within at least one selected from the plurality of fission fuel subassemblies.

  [88] For a selection from the plurality of fission fuel subassemblies, determining the movement from a first position to a second position along a respective first dimension is selected from the plurality of fission fuel subassemblies. Determining the radial movement from a first position to a second position along a respective first dimension for the first and second dimensions.

  [89] determining a movement from a first position to a second position along a respective first dimension for the selected from the plurality of fission fuel subassemblies is selected from the plurality of fission fuel subassemblies; Determining the spiral movement from a first position to a second position along a respective first dimension.

  [90] For a selection from the plurality of fission fuel subassemblies, determining the movement from a first position to a second position along a respective first dimension is selected from the plurality of fission fuel subassemblies. [51] The method according to [51], comprising determining an axial translation of

  [91] The method according to [51], wherein determining the desired shape of the combustion wave front of the fission traveling wave includes determining a substantially spherical shape of the combustion wave front of the fission traveling wave.

  [92] Determining a desired shape of the combustion wavefront of the fission traveling wave along the second dimension includes determining a continuous curved surface shape of the combustion wavefront of the fission traveling wave, [51] The method described.

  [93] The method according to [51], wherein the desired shape of the combustion wavefront of the fission traveling wave is substantially rotationally symmetric with respect to the second dimension.

  [94] The method according to [51], wherein the desired shape of the combustion wavefront of the fission traveling wave is substantially n-fold rotationally symmetric with respect to the second dimension.

  [95] The method according to [51], wherein the desired shape of the combustion wavefront of the fission traveling wave is asymmetric.

  [96] The method according to [95], wherein the desired shape of the combustion wavefront of the fission traveling wave is rotationally asymmetric with respect to the second dimension.

[97] For the combustion wavefront of the fission traveling wave propagating along the first dimension and the second dimension, along the second dimension in a plurality of fission fuel subassemblies based on a selected set of dimensional constraints. A first electrical circuit configured to determine a desired shape of a combustion wavefront of a fission traveling wave;
A selection from the plurality of nuclear fission fuel subassemblies is configured to determine movement from a first position to a second position along a respective first dimension to correspond to the desired shape. A system comprising: a second electrical circuit;

  [98] The system according to [97], wherein the second electric circuit is further configured to determine an existing shape of a combustion wavefront of the fission traveling wave.

  [99] The second electrical circuit may further include a second position from a first position along a respective first dimension so as to build the desired shape for the one selected from the plurality of fission fuel subassemblies. The system of [97], configured to determine movement to a location.

  [100] The second electrical circuit further includes a second selected from the first position along each first dimension so as to maintain the desired shape for the one selected from the plurality of fission fuel subassemblies. The system of [97], configured to determine movement to a location.

  [101] The second electrical circuit may further include a second selected from the plurality of nuclear fission fuel subassemblies from the first position along the first dimension so as to correspond to the desired shape. The system of [97], configured to determine when to move to a position.

  [102] The system of [97], wherein the plurality of nuclear fission fuel subassemblies extend along the second dimension.

  [103] The system of [97], wherein the first dimension is substantially orthogonal to a major axis of the plurality of fission fuel subassemblies.

  [104] The system according to [97], wherein the first dimension and the second dimension are substantially perpendicular to each other.

[105] The system according to [97], wherein the first dimension includes a radial dimension, and the second dimension includes an axial dimension.

[106] The system according to [97], wherein the first dimension includes an axial dimension, and the second dimension includes a radial dimension.

[107] The system according to [97], wherein the first dimension includes an axial dimension, and the second dimension includes a lateral dimension.

[108] The system according to [97], wherein the first dimension includes a lateral dimension, and the second dimension includes an axial dimension.

[109] The system of [97], wherein the first position includes an outer position, and the second position includes an inner position.

  [110] The system according to [109], wherein the inner position and the outer position are based on a geometric approximation to a central portion of the core of the reactor.

  [111] The system according to [109], wherein the inner position and the outer position are based on a neutron flux such that a neutron flux at the inner position is larger than a neutron flux at the outer position.

[112] The system according to [109], wherein the inner position and the outer position are based on a reactivity such that k _{effective at} the inner position is larger than k _{effective at the} outer position.

[113] The system according to [97], wherein the first position includes an inner position, and the second position includes an outer position.

  [114] The system according to [113], wherein the inner position and the outer position are based on a geometric approximation to a central portion of the core of the reactor.

  [115] The system according to [113], wherein the inner position and the outer position are based on a neutron flux such that a neutron flux at the inner position is larger than a neutron flux at the outer position.

[116] The system according to [113], wherein the inner position and the outer position are based on a reactivity such that k _{effective at} the inner position is larger than k _{effective at the} outer position.

  [117] The system according to [97], wherein the first position and the second position are located on opposite sides of the reference value along the first dimension.

  [118] The system of [97], wherein the first position and the second position include at least one attribute that is substantially equalized.

  [119] The system of [118], wherein the at least one attribute includes a geometric approximation to a central region of the reactor core.

  [120] The system of [118], wherein the at least one attribute includes a neutron flux.

  [121] The system according to [118], wherein the at least one attribute includes reactivity.

  [122] The system of [97], wherein the second electrical circuit is further configured to determine a rotation of at least one selected from the plurality of fission fuel subassemblies.

  [123] The system of [97], wherein the second electrical circuit is further configured to determine an inversion of at least one selected from the plurality of fission fuel subassemblies.

  [124] The system of [97], wherein the selected set of dimension restrictions includes a predetermined maximum distance along the second dimension.

  [125] The system of [97], wherein the selected set of dimension limits is a function of at least one combustion wavefront standard.

  [126] The system according to [125], wherein the combustion wavefront standard includes a neutron flux.

  [127] The system of [126], wherein the neutron flux is associated with at least one selected from the plurality of fission fuel subassemblies.

  [128] The system according to [125], wherein the combustion wavefront standard includes a neutron fluence.

  [129] The system of [128], wherein the neutron fluence is associated with at least one selected from the plurality of fission fuel subassemblies.

  [130] The system according to [125], wherein the combustion wavefront standard includes a burnup degree.

  [131] The system of [130], wherein the burnup is related to at least one selected from the plurality of fission fuel subassemblies.

  [132] The system of [125], wherein the combustion wavefront standard includes a combustion wavefront position within at least one selected from the plurality of fission fuel subassemblies.

  [133] The second electrical circuit further determines radial movement from a first position to a second position along a respective first dimension for a selection from the plurality of fission fuel subassemblies. The system according to [97], configured as described above.

  [134] The second electrical circuit is further configured to determine a spiral movement from a first position to a second position along a respective first dimension for a selection from the plurality of fission fuel subassemblies. The system according to [97], which is configured.

  [135] The system of [97], wherein the second electrical circuit is further configured to determine an axial translation for a selection from the plurality of fission fuel subassemblies.

  [136] The system according to [97], wherein the first electric circuit is further configured to determine a substantially spherical shape of a combustion wavefront of the fission traveling wave.

  [137] The system according to [97], wherein the first electric circuit is further configured to determine a continuous curved surface shape of the combustion wavefront of the fission traveling wave.

  [138] The system according to [97], wherein the desired shape of the combustion wavefront of the fission traveling wave is substantially rotationally symmetric with respect to the second dimension.

  [139] The system according to [97], wherein the desired shape of the combustion wavefront of the fission traveling wave is substantially n-fold rotationally symmetric with respect to the second dimension.

  [140] The system according to [97], wherein the desired shape of the combustion wavefront of the fission traveling wave is asymmetric.

  [141] The system according to [97], wherein a desired shape of the combustion wavefront of the fission traveling wave is rotationally asymmetric with respect to the second dimension.

[142] A combustion wavefront of a fission traveling wave propagating along the first dimension and the second dimension, along the second dimension, within a plurality of fission fuel subassemblies, based on a selected set of dimensional constraints. First computer readable medium software program code configured to determine a desired shape of a combustion wavefront of a fission traveling wave;
A selection from the plurality of nuclear fission fuel subassemblies is configured to determine movement from a first position to a second position along a respective first dimension to correspond to the desired shape. A computer software program product comprising: a second computer readable medium software program code.

  [143] The computer software program product according to [142], wherein the second computer readable medium software program code is further configured to determine an existing shape of the combustion wavefront of the fission traveling wave.

  [144] The second computer readable medium software program code further includes a first one along each first dimension so as to construct the desired shape for the one selected from the plurality of fission fuel subassemblies. The computer software program product of [142] configured to determine movement from a position to a second position.

  [145] The second computer readable medium software program code further includes a first one along each first dimension to maintain the desired shape for one selected from the plurality of fission fuel subassemblies. The computer software program product of [142] configured to determine movement from a position to a second position.

  [146] The second computer readable medium software program code further includes a first selected along the first dimension so as to correspond to the desired shape for one selected from the plurality of fission fuel subassemblies. The computer software program product of [142], configured to determine when to move from a position to a second position.

  [147] The computer software program product according to [142], wherein the plurality of fission fuel subassemblies extend along the second dimension.

  [148] The computer software program product according to [142], wherein the first dimension is substantially orthogonal to a major axis of the plurality of fission fuel subassemblies.

  [149] The computer software program product according to [142], wherein the first dimension and the second dimension are substantially perpendicular to each other.

[150] The computer software program product according to [142], wherein the first dimension includes a radial dimension, and the second dimension includes an axial dimension.

[151] The computer software program product according to [142], wherein the first dimension includes an axial dimension, and the second dimension includes a radial dimension.

[152] The computer software program product according to [142], wherein the first dimension includes an axial dimension, and the second dimension includes a lateral dimension.

[153] The computer software program product according to [142], wherein the first dimension includes a lateral dimension, and the second dimension includes an axial dimension.

[154] The computer software program product according to [142], wherein the first position includes an outer position, and the second position includes an inner position.

  [155] The computer software program product according to [154], wherein the inner position and the outer position are based on a geometric approximation to a central portion of the reactor core.

  [156] The computer software program product according to [154], wherein the inner position and the outer position are based on a neutron flux such that the neutron flux at the inner position is larger than the neutron flux at the outer position.

[157] The computer software program product according to [154], wherein the inner position and the outer position are based on a reactivity such that k _{effective at} the inner position is larger than k _{effective at the} outer position.

[158] The computer software program product according to [142], wherein the first position includes an inner position, and the second position includes an outer position.

  [159] The computer software program product according to [158], wherein the inner position and the outer position are based on a geometric approximation to a central portion of the reactor core.

  [160] The computer software program product according to [158], wherein the inner position and the outer position are based on a neutron flux such that the neutron flux at the inner position is larger than the neutron flux at the outer position.

[161] The computer software program product according to [158], wherein the inner position and the outer position are based on a reactivity such that k _{effective at} the inner position is larger than k _{effective at the} outer position.

  [162] The computer software program product according to [142], wherein the first position and the second position are located on opposite sides of the reference value along the first dimension.

  [163] The computer software program product according to [142], wherein the first position and the second position include at least one attribute that is substantially equalized.

  [164] The computer software program product according to [163], wherein the at least one attribute includes a geometric approximation to a central region of the reactor core.

  [165] The computer software program product according to [163], wherein the at least one attribute includes a neutron flux.

  [166] The computer software program product according to [163], wherein the at least one attribute includes reactivity.

  [167] The computer software program product of [142], wherein the second electrical circuit is further configured to determine at least one rotation of one selected from the plurality of fission fuel subassemblies.

  [168] The computer software program product of [142], wherein the second electrical circuit is further configured to determine an inversion of at least one selected from the plurality of fission fuel subassemblies.

  [169] The computer software program product according to [142], wherein the selected set of dimension restrictions includes a predetermined maximum distance along the second dimension.

  [170] The computer software program product of [142], wherein the selected set of dimensional constraints is a function of at least one combustion wavefront standard.

  [171] The computer software program product according to [170], wherein the combustion wavefront standard includes a neutron flux.

  [172] The computer software program product of [171], wherein the neutron flux is associated with at least one selected from the plurality of fission fuel subassemblies.

  [173] The computer software program product according to [170], wherein the combustion wavefront standard includes a neutron fluence.

  [174] The computer software program product of [173], wherein the neutron fluence is associated with at least one selected from the plurality of fission fuel subassemblies.

  [175] The computer software program product according to [170], wherein the combustion wavefront standard includes burnup.

  [176] The computer software program product of [175], wherein the burnup is associated with at least one selected from the plurality of fission fuel subassemblies.

  [177] The computer software program product of [170], wherein the combustion wavefront standard includes a combustion wavefront position within at least one selected from the plurality of fission fuel subassemblies.

  [178] The second computer readable medium software program code for the one selected from the plurality of fission fuel subassemblies for radial movement from a first position to a second position along a respective first dimension. The computer software program product of [142], comprising third computer readable medium software program code configured to determine.

  [179] The second computer readable media software program code determines a helical movement from a first position to a second position along a respective first dimension for a selection from the plurality of fission fuel subassemblies. The computer software program product according to [142], comprising a fourth computer-readable medium software program code configured as described above.

  [180] The second computer readable medium software program code includes fifth computer readable medium software program code configured to determine axial translation for a selection from the plurality of fission fuel subassemblies. [142] A computer software program product.

  [181] The first computer readable medium software program code includes the seventh computer readable medium software program code configured to determine a substantially spherical shape of the combustion wavefront of the fission traveling wave. Computer software program product.

  [182] The first computer readable medium software program code includes an eighth computer readable medium software program code configured to determine a continuous curved shape of the combustion wavefront of the fission traveling wave. [142] The computer software program product described.

  [183] The computer software program product according to [142], wherein the desired shape of the combustion wavefront of the fission traveling wave is substantially rotationally symmetric with respect to the second dimension.

  [184] The computer software program product according to [142], wherein the desired shape of the combustion wavefront of the fission traveling wave is substantially n-fold rotationally symmetric with respect to the second dimension.

  [185] The computer software program product according to [142], wherein the desired shape of the combustion wavefront of the fission traveling wave is asymmetric.

  [186] The computer software program product according to [185], wherein the desired shape of the combustion wavefront of the fission traveling wave is rotationally asymmetric with respect to the second dimension.

[187] For the combustion wavefront of the fission traveling wave propagating along the first dimension and the second dimension, along the second dimension in a plurality of fission fuel subassemblies, based on a selected set of dimensional constraints. A first electrical circuit configured to determine a desired shape of a combustion wavefront of a fission traveling wave;
A selection from the plurality of nuclear fission fuel subassemblies is configured to determine movement from a first position to a second position along a respective first dimension to correspond to the desired shape. A second electrical circuit;
A subassembly configured to move a selected one of the plurality of fission fuel subassemblies in response to the second electrical circuit.

  [188] The system according to [187], wherein the second electric circuit is further configured to determine an existing shape of the combustion wavefront of the fission traveling wave.

  [189] The second electrical circuit further includes a second position from a first position along a respective first dimension so as to build the desired shape for the one selected from the plurality of fission fuel subassemblies. The system of [187], wherein the system is configured to determine movement to a position.

  [190] The second electrical circuit further includes a second selected from the first position along each first dimension so as to maintain the desired shape for the one selected from the plurality of fission fuel subassemblies. The system of [187], wherein the system is configured to determine movement to a position.

  [191] The second electrical circuit further includes a second selected one of the plurality of fission fuel subassemblies from the first position along the first dimension so as to correspond to the second shape so as to correspond to the desired shape. The system of [187], wherein the system is configured to determine when to move to a position.

  [192] The system of [187], wherein the plurality of fission fuel subassemblies extend along the second dimension.

  [193] The system of [187], wherein the first dimension is substantially orthogonal to a major axis of the plurality of fission fuel subassemblies.

  [194] The system according to [187], wherein the first dimension and the second dimension are substantially perpendicular to each other.

[195] The system according to [187], wherein the first dimension includes a radial dimension, and the second dimension includes an axial dimension.

[196] The system according to [187], wherein the first dimension includes an axial dimension, and the second dimension includes a radial dimension.

[197] The system according to [187], wherein the first dimension includes an axial dimension, and the second dimension includes a lateral dimension.

[198] The system according to [187], wherein the first dimension includes a lateral dimension, and the second dimension includes an axial dimension.

[199] The system of [187], wherein the first position includes an outer position, and the second position includes an inner position.

  [200] The system according to [199], wherein the inner position and the outer position are based on a geometric approximation to a central portion of the core of the reactor.

  [201] The system according to [199], wherein the inner position and the outer position are based on a neutron flux such that a neutron flux at the inner position is larger than a neutron flux at the outer position.

[202] The system according to [199], wherein the inner position and the outer position are based on a reactivity such that k _{effective at} the inner position is larger than k _{effective at the} outer position.

[203] The system according to [187], wherein the first position includes an inner position, and the second position includes an outer position.

  [204] The system according to [203], wherein the inner position and the outer position are based on a geometric approximation to a central portion of the reactor core.

  [205] The system according to [203], wherein the inner position and the outer position are based on a neutron flux such that a neutron flux at the inner position is larger than a neutron flux at the outer position.

[206] The system according to [203], wherein the inner position and the outer position are based on a reactivity such that k _{effective at} the inner position is larger than k _{effective at the} outer position.

  [207] The system according to [187], wherein the first position and the second position are located on opposite sides of the reference value along the first dimension.

  [208] The system of [187], wherein the first position and the second position include at least one attribute that is substantially equalized.

  [209] The system of [208], wherein the at least one attribute includes a geometric approximation to a central region of the reactor core.

  [210] The system according to [208], wherein the at least one attribute includes a neutron flux.

  [211] The system according to [208], wherein the at least one attribute includes reactivity.

  [212] The system of [187], wherein the second electrical circuit is further configured to determine at least one rotation of a selection from the plurality of fission fuel subassemblies.

  [213] The system of [187], wherein the second electrical circuit is further configured to determine an inversion of at least one selected from the plurality of fission fuel subassemblies.

  [214] The system according to [187], wherein the subassembly includes a nuclear fuel handling device.

  [215] The method according to [187], wherein the subassembly is further configured to radially move each of the plurality of fission fuel subassemblies selected from the first position to the second position. system.

  [216] The system of [187], wherein the subassembly is further configured to spirally move each selected from the plurality of fission fuel subassemblies from a first position to a second position.

  [217] The system of [187], wherein the subassembly is further configured to axially translate a selected one of the plurality of fission fuel subassemblies.

  [218] The system of [187], wherein the subassembly is further configured to rotate with respect to a selection from the plurality of fission fuel subassemblies.

  [219] The system of [187], wherein the subassembly is further configured to invert a selected one of the plurality of fission fuel subassemblies.

[220] a traveling wave fission reactor core;
A plurality of fission fuel subassemblies received within the core of the traveling wave fission reactor, each configured to propagate a combustion wavefront of a fission traveling wave along a first dimension and a second dimension within the core When,
A first electrical circuit configured to determine a desired shape of a fission traveling wave combustion wavefront along the second dimension within a plurality of fission fuel subassemblies based on a selected set of dimensional constraints;
A selection from the plurality of nuclear fission fuel subassemblies is configured to determine movement from a first position to a second position along a respective first dimension to correspond to the desired shape. A second electrical circuit;
A traveling wave fission reactor comprising: a subassembly configured to move a selected one of the plurality of fission fuel subassemblies corresponding to the second electrical circuit.

  [221] The reactor according to [220], wherein the second electric circuit is further configured to determine an existing shape of a combustion wavefront of the fission traveling wave.

  [222] The second electrical circuit further includes a second position from a first position along a respective first dimension so as to build the desired shape for the selected one of the plurality of fission fuel subassemblies. The reactor according to [220], which is configured to determine movement to a position.

  [223] The second electrical circuit further includes a second selected from the first position along each first dimension so as to maintain the desired shape for the one selected from the plurality of fission fuel subassemblies. The reactor according to [220], which is configured to determine movement to a position.

  [224] The second electrical circuit further includes a second electrical circuit selected from the plurality of fission fuel subassemblies, each corresponding to the desired shape, from the first position to the second position so as to correspond to the desired shape. The reactor according to [220], which is configured to determine when to move to a position.

  [225] The reactor according to [220], wherein the plurality of fission fuel subassemblies extend along the second dimension.

  [226] The reactor according to [220], wherein the first dimension is substantially orthogonal to a major axis of the plurality of fission fuel subassemblies.

  [227] The reactor according to [220], wherein the first dimension and the second dimension are substantially perpendicular to each other.

[228] The reactor according to [220], wherein the first dimension includes a radial dimension, and the second dimension includes an axial dimension.

[229] The reactor according to [220], wherein the first dimension includes an axial dimension, and the second dimension includes a radial dimension.

[230] The reactor according to [220], wherein the first dimension includes an axial dimension, and the second dimension includes a lateral dimension.

[231] The reactor according to [220], wherein the first dimension includes a lateral dimension, and the second dimension includes an axial dimension.

[232] The reactor according to [220], wherein the first position includes an outer position, and the second position includes an inner position.

  [233] The reactor according to [232], wherein the inner position and the outer position are based on a geometric approximation to a central portion of the reactor core.

  [234] The reactor according to [232], wherein the inner position and the outer position are based on a neutron flux such that a neutron flux at the inner position is larger than a neutron flux at the outer position.

[235] The reactor according to [232], wherein the inner position and the outer position are based on a reactivity such that k _{effective at} the inner position is larger than k _{effective at the} outer position.

[236] The reactor according to [220], wherein the first position includes an inner position, and the second position includes an outer position.

  [237] The reactor according to [236], wherein the inner position and the outer position are based on a geometric approximation with respect to a central portion of the reactor core.

  [238] The reactor according to [236], wherein the inner position and the outer position are based on a neutron flux such that a neutron flux at the inner position is larger than a neutron flux at the outer position.

[239] The reactor according to [236], wherein the inner position and the outer position are based on a reactivity such that k _{effective at} the inner position is larger than k _{effective at the} outer position.

  [240] The reactor according to [220], wherein the first position and the second position are located on opposite sides of the reference value along the first dimension.

  [241] The reactor according to [220], wherein the first position and the second position include at least one attribute that is substantially equalized.

  [242] The reactor according to [241], wherein the at least one attribute includes a geometric approximation to a central region of the reactor core.

  [243] The reactor according to [241], wherein the at least one attribute includes a neutron flux.

  [244] The reactor according to [241], wherein the at least one attribute includes reactivity.

  [245] The reactor according to [220], wherein the second electric circuit is further configured to determine at least one rotation among those selected from the plurality of fission fuel subassemblies.

  [246] The reactor according to [220], wherein the second electric circuit is further configured to determine an inversion of at least one selected from the plurality of fission fuel subassemblies.

  [247] The reactor according to [220], wherein the selected set of dimension limits includes a predetermined maximum distance along the second dimension.

  [248] The reactor of [220], wherein the selected set of dimensional limits is a function of at least one combustion wavefront standard.

  [249] The reactor according to [248], wherein the combustion wavefront standard includes a neutron flux.

  [250] The reactor according to [249], wherein the neutron flux is related to at least one selected from the plurality of fission fuel subassemblies.

  [251] The reactor according to [248], wherein the combustion wavefront standard includes a neutron fluence.

  [252] The reactor according to [251], wherein the neutron fluence is related to at least one selected from the plurality of fission fuel subassemblies.

  [253] The reactor according to [248], wherein the combustion wavefront standard includes a burnup degree.

  [254] The reactor according to [253], wherein the burnup is related to at least one selected from the plurality of fission fuel subassemblies.

  [255] The reactor according to [248], wherein the combustion wavefront standard includes a combustion wavefront position within at least one selected from the plurality of fission fuel subassemblies.

  [256] The second electrical circuit further determines radial movement from a first position to a second position along a respective first dimension for a selection from the plurality of fission fuel subassemblies. The reactor according to [220], configured as described above.

  [257] The second electrical circuit is further configured to determine a spiral movement from a first position to a second position along a respective first dimension for a selection from the plurality of fission fuel subassemblies. The reactor according to [220], which is configured.

  [258] The reactor according to [220], wherein the second electric circuit is further configured to determine an axial translation of a selected one of the plurality of fission fuel subassemblies.

  [259] The reactor according to [220], wherein the first electric circuit is further configured to determine a substantially spherical shape of a combustion wavefront of the fission traveling wave.

  [260] The reactor according to [220], wherein the first electric circuit is further configured to determine a continuous curved surface shape of the combustion wavefront of the fission traveling wave.

  [261] The reactor according to [220], wherein a desired shape of the combustion wavefront of the fission traveling wave is substantially rotationally symmetric with respect to the second dimension.

  [262] The reactor according to [220], wherein a desired shape of the combustion wave front of the fission traveling wave is substantially n-fold rotationally symmetric with respect to the second dimension.

  [263] The reactor according to [220], wherein a desired shape of the combustion wave front of the fission traveling wave is asymmetric.

  [264] The reactor according to [263], wherein a desired shape of the combustion wavefront of the fission traveling wave is rotationally asymmetric with respect to the second dimension.

  [265] The reactor according to [220], wherein the subassembly includes a nuclear fuel handling device.

  [266] The subassembly according to [220], wherein the subassembly is further configured to radially move each selected from the plurality of fission fuel subassemblies from a first position to a second position. Reactor.

  [267] The reactor according to [220], wherein the subassembly is further configured to spirally move each of the plurality of fission fuel subassemblies selected from the first position to the second position. .

  [268] The reactor according to [220], wherein the subassembly is further configured to axially translate a selected one of the plurality of fission fuel subassemblies.

  [269] The reactor according to [220], wherein the subassembly is further configured to rotate with respect to one selected from the plurality of fission fuel subassemblies.

  [270] The reactor according to [220], wherein the subassembly is further configured to invert a selected one of the plurality of fission fuel subassemblies.

  [271] A traveling wave fission reaction comprising moving at least one fission fuel subassembly outward from a first position in the traveling wave fission reactor core to a second position in the traveling wave fission reactor core. How to operate the furnace.

  [272] The method of [271], further comprising moving at least one fission fuel subassembly inwardly from the second position.

  [273] The method according to [271], wherein the first position and the second position are based on a geometric approximation with respect to a central portion of the reactor core.

  [274] The method according to [271], wherein the first position and the second position are based on a neutron flux such that a neutron flux at the first position is larger than a neutron flux at the second position.

[275] The method according to [271], wherein the first position and the second position are based on a reactivity such that k _{effective at} the first position is larger than k _{effective at} the second position.

[276] For at least one fission fuel subassembly, in a first direction from a first position in the traveling wave fission reactor core to a second position different from the first position in the traveling wave fission reactor core. Deciding to move,
Determining a movement of the at least one fission fuel subassembly from the second position in a second direction different from the first direction.

[277] The method according to [276], wherein the first direction is an outer direction, and the second direction is an inner direction.

  [278] The method according to [277], wherein the first position and the second position are based on a geometric approximation with respect to a central portion of the reactor core.

  [279] The method according to [277], wherein the first position and the second position are based on a neutron flux such that a neutron flux at the first position is larger than a neutron flux at the second position.

[280] The method according to [277], wherein the first position and the second position are based on a reactivity such that k _{effective at} the first position is larger than k _{effective at} the second position.

  [281] The method according to [276], wherein the first direction is an inner direction and the second direction is an outer direction.

  [282] The method according to [281], wherein the second position and the first position are based on a geometric approximation to a central portion of the reactor core.

  [283] The method according to [281], wherein the second position and the first position are based on a neutron flux such that a neutron flux at the second position is larger than a neutron flux at the first position.

[284] The method according to [281], wherein the second position and the first position are based on a reactivity such that k _{effective at} the second position is larger than k _{effective at} the first position.

[285] At least one fission fuel subassembly in a first direction from a first position in the traveling wave fission reactor core to a second position different from the first position in the traveling wave fission reactor core. Moving it,
Determining a movement of the at least one fission fuel subassembly from the second position in a second direction different from the first direction.

  [286] The method according to [285], wherein the first direction is an outer direction and the second direction is an inner direction.

  [287] The method according to [286], wherein the first position and the second position are based on a geometric approximation with respect to a central portion of the reactor core.

  [288] The method according to [286], wherein the first position and the second position are based on a neutron flux such that a neutron flux at the first position is larger than a neutron flux at the second position.

[289] The method according to [286], wherein the first position and the second position are based on a reactivity such that k _{effective at} the first position is larger than k _{effective at} the second position.

[290] The method according to [285], wherein the first direction is an inner direction, and the second direction is an outer direction.

  [291] The method according to [290], wherein the second position and the first position are based on a geometric approximation to a central portion of the reactor core.

  [292] The method according to [290], wherein the second position and the first position are based on a neutron flux such that a neutron flux at the second position is larger than a neutron flux at the first position.

[293] The method according to [290], wherein the second position and the first position are based on a reactivity such that k _{effective at} the second position is larger than k _{effective at} the first position.

[294] moving at least one fission fuel subassembly in a first direction from a first position in the traveling wave fission reactor to a second position different from the first position in the traveling wave fission reactor; ,
Moving at least one fission fuel subassembly from the second position in a second direction different from the first direction.

[295] The method according to [294], wherein the first direction is an outer direction, and the second direction is an inner direction.

  [296] The method according to [295], wherein the first position and the second position are based on a geometric approximation to a central portion of the reactor core.

  [297] The method according to [295], wherein the first position and the second position are based on a neutron flux such that a neutron flux at the first position is larger than a neutron flux at the second position.

[298] The method of [295], wherein the first position and the second position are based on a reactivity such that k _{effective at} the first position is greater than k _{effective at} the second position.

[299] The method according to [294], wherein the first direction is an inner direction, and the second direction is an outer direction.

  [300] The method according to [299], wherein the second position and the first position are based on a geometric approximation to a central portion of the reactor core.

  [301] The method according to [299], wherein the second position and the first position are based on a neutron flux such that a neutron flux at the second position is larger than a neutron flux at the first position.

[302] The method according to [299], wherein the second position and the first position are based on a reactivity such that k _{effective at} the second position is larger than k _{effective at} the first position.

[303] selecting a predetermined burnup level;
Determining, for all of the plurality of fission fuel subassemblies, the movement of a selected one of the plurality of fission fuel subassemblies within the core of the fission reactor such that the burnup level is at the predetermined burnup level. Including a method of operating a traveling wave fission reactor.

  [304] The method of [303], further comprising moving a selected one of a plurality of fission fuel subassemblies in a nuclear fission reactor core in response to the determined movement.

  [305] The method according to [304], further comprising: determining the removal of each selected from the plurality of fission fuel subassemblies when the burnup level becomes equal to the predetermined burnup level. the method of.

  [306] The method of [305], further comprising removing a selected one of the plurality of fission fuel subassemblies in response to the determined removal.

  While various aspects and embodiments have been disclosed herein, other aspects and embodiments will be apparent to those skilled in the art. Also, while various aspects and embodiments have been disclosed herein, those skilled in the art will appreciate that other aspects and embodiments are possible. The various aspects and embodiments disclosed herein are for purposes of illustration and are not intended to be limiting. The true scope and spirit of the invention is indicated by the following claims.

1 is a block diagram of an exemplary method of operating a traveling wave fission reactor. FIG. 1 is a perspective view of a partial schematic configuration of core components of an exemplary fission reactor. FIG. 1 is a perspective view of a partial schematic configuration of core components of an exemplary fission reactor. FIG. 1 is a perspective view of a partial schematic configuration of core components of an exemplary fission reactor. FIG. The influence of the combustion wavefront shape of the fission traveling wave due to the movement of the selected fission fuel subassembly is shown. The influence of the combustion wavefront shape of the fission traveling wave due to the movement of the selected fission fuel subassembly is shown. The influence of the combustion wavefront shape of the fission traveling wave due to the movement of the selected fission fuel subassembly is shown. The influence of the combustion wavefront shape of the fission traveling wave due to the movement of the selected fission fuel subassembly is shown. FIG. 1B is a block diagram detailing a portion of the method of FIG. 1A. Fig. 4 shows the rotation of the fission fuel subassembly. FIG. 1B is a block diagram detailing a portion of the method of FIG. 1A. Fig. 5 shows a reversal of the fission fuel subassembly. FIG. 1B is a block diagram detailing a portion of the method of FIG. 1A. FIG. 1B is a block diagram detailing a portion of the method of FIG. 1A. Fig. 5 shows spiral movement of a fission fuel subassembly. FIG. 1B is a block diagram detailing a portion of the method of FIG. 1A. Fig. 3 shows the axial movement of the fission fuel subassembly. The substantially spherical shape of the combustion wave front of a fission traveling wave is shown. The continuous curved surface shape of the combustion wave front of the fission traveling wave is shown. A substantially rotationally symmetric shape of the combustion wave front of the fission traveling wave is shown. A substantially n-fold rotationally symmetric shape of the combustion wave front of the fission traveling wave is shown. A substantially n-fold rotationally symmetric shape of the combustion wave front of the fission traveling wave is shown. FIG. 1B is a block diagram detailing a portion of the method of FIG. 1A. FIG. 1B is a block diagram detailing a portion of the method of FIG. 1A. FIG. 1B is a block diagram detailing a portion of the method of FIG. 1A. FIG. 1B is a block diagram detailing a portion of the method of FIG. 1A. FIG. 1B is a block diagram detailing a portion of the method of FIG. 1A. FIG. 1B is a block diagram detailing a portion of the method of FIG. 1A. FIG. 1B is a block diagram detailing a portion of the method of FIG. 1A. FIG. 1B is a block diagram detailing a portion of the method of FIG. 1A. FIG. 1B is a block diagram detailing a portion of the method of FIG. 1A. 1 is a block diagram of an exemplary control method for a traveling wave fission reactor. FIG. 2B is a block diagram detailing a portion of the method of FIG. 2A. FIG. 2B is a block diagram detailing a portion of the method of FIG. 2A. FIG. 2B is a block diagram detailing a portion of the method of FIG. 2A. FIG. 2B is a block diagram detailing a portion of the method of FIG. 2A. FIG. 2B is a block diagram detailing a portion of the method of FIG. 2A. FIG. 2B is a block diagram detailing a portion of the method of FIG. 2A. FIG. 2B is a block diagram detailing a portion of the method of FIG. 2A. FIG. 2B is a block diagram detailing a portion of the method of FIG. 2A. FIG. 2B is a block diagram detailing a portion of the method of FIG. 2A. FIG. 2B is a block diagram detailing a portion of the method of FIG. 2A. FIG. 2B is a block diagram detailing a portion of the method of FIG. 2A. FIG. 2B is a block diagram detailing a portion of the method of FIG. 2A. FIG. 1 is a block diagram of an exemplary system for determining the movement of a fission fuel subassembly. FIG. FIG. 3B is a block diagram illustrating in detail the components of the system of FIG. 3A. FIG. 3B is a block diagram illustrating in detail the components of the system of FIG. 3A. 1 is a block diagram of an exemplary system for moving a fission fuel subassembly. FIG. FIG. 4B is a block diagram illustrating in detail the components of the system of FIG. 4A. FIG. 4B is a block diagram illustrating in detail the components of the system of FIG. 4A. 1 is a block diagram of a partial schematic configuration of an exemplary traveling wave fission reactor. FIG. 2 is a flowchart of an exemplary method of operating a traveling wave fission reactor. FIG. 6B is a block diagram detailing a portion of the method of FIG. 6A. 2 is a flowchart of an exemplary method of operating a traveling wave fission reactor. 2 is a flowchart of an exemplary method of operating a traveling wave fission reactor. 2 is a flowchart of an exemplary method of operating a traveling wave fission reactor. 2 is a flowchart of an exemplary method of operating a fission reactor. FIG. 10B is a block diagram detailing a portion of the method of FIG. 10A. FIG. 10B is a block diagram detailing a portion of the method of FIG. 10A. FIG. 10B is a block diagram detailing a portion of the method of FIG. 10A.

Claims (106)

Fission progression along the second dimension in a plurality of fission fuel subassemblies based on a selected set of dimensional constraints on the combustion wavefront of the fission traveling wave propagating along the first and second dimensions Determining the desired shape of the wave combustion wavefront;
Determining a movement from a first position to a second position along a respective first dimension for a selected one of the plurality of fission fuel subassemblies to correspond to the desired shape. How to control a traveling wave fission reactor.   The method of claim 1, further comprising determining an existing shape of the combustion wavefront of the fission traveling wave.   Determining the movement from the first position to the second position along each first dimension for the selected one of the plurality of fission fuel subassemblies to correspond to the desired shape is the plurality Determining a movement from a first position to a second position along a respective first dimension for the selected one of the fission fuel subassemblies to build the desired shape. The method according to 1.   Determining the movement from the first position to the second position along each first dimension for the selected one of the plurality of fission fuel subassemblies to correspond to the desired shape is the plurality Determining a movement from a first position to a second position along a respective first dimension so as to maintain the desired shape for a selected one of the nuclear fission fuel subassemblies. The method according to 1.   And determining when to move each of the fission fuel subassemblies from the first position to the second position along the first dimension so as to correspond to the desired shape. The method of claim 1 comprising.   And moving each selected from the plurality of nuclear fission fuel subassemblies along a first dimension from a first position to a second position to correspond to the desired shape. The method of claim 1.   The method of claim 1, wherein the first dimension is substantially orthogonal to a major axis of the plurality of fission fuel subassemblies.   The method of claim 1, wherein the first dimension and the second dimension are substantially perpendicular to each other. The method of claim 1, wherein the first dimension includes a radial dimension, and the second dimension includes an axial dimension. The method of claim 1, wherein the first dimension includes an axial dimension, and the second dimension includes a radial dimension. The method of claim 1, wherein the first dimension includes an axial dimension, and the second dimension includes a lateral dimension. The method of claim 1, wherein the first dimension includes a lateral dimension, and the second dimension includes an axial dimension. The method of claim 1, wherein the first position includes an outer position and the second position includes an inner position. The inner position and the outer position are geometric approximations to the center of the reactor core, the neutron flux is such that the neutron flux at the inner position is larger than the neutron flux at the outer position, and the k _{effective at the} inner position is _14. The method of claim 13, based on at least one attribute selected from a reactivity that is greater than k _{effective at the} outer location. The method of claim 1, wherein the first position includes an inner position and the second position includes an outer position. The inner position and the outer position are geometric approximations to the center of the reactor core, the neutron flux is such that the neutron flux at the inner position is larger than the neutron flux at the outer position, and the k _{effective at the} inner position is 16. The method of claim 15, based on at least one attribute selected from a reactivity that is greater than k _{effective at the} outer location.   The method of claim 1, wherein the first position and the second position are located on opposite sides of a reference value along the first dimension.   The method of claim 1, wherein the first location and the second location include at least one attribute that is substantially equalized.   The method of claim 18, wherein the at least one attribute comprises an attribute selected from a geometric approximation to a central region of the reactor core, a neutron flux, and a reactivity.   Determining the movement from a first position to a second position along a respective first dimension for a selection from the plurality of fission fuel subassemblies is selected from the plurality of fission fuel subassemblies The method of claim 1, comprising determining at least one of the rotations.   Determining the movement from a first position to a second position along a respective first dimension for a selection from the plurality of fission fuel subassemblies is selected from the plurality of fission fuel subassemblies The method of claim 1, comprising determining at least one inversion.   The method of claim 1, wherein the selected set of dimensional constraints includes a predetermined maximum distance along the second dimension.   The method of claim 1, wherein the selected set of dimensional constraints is a function of at least one combustion wavefront standard.   24. The method of claim 23, wherein the combustion wavefront standard includes a neutron flux.   25. The method of claim 24, wherein the neutron flux is associated with at least one selected from the plurality of fission fuel subassemblies.   24. The method of claim 23, wherein the combustion wavefront standard includes a neutron fluence.   27. The method of claim 26, wherein the neutron fluence is associated with at least one selected from the plurality of fission fuel subassemblies.   24. The method of claim 23, wherein the combustion wavefront standard includes burnup.   30. The method of claim 28, wherein the burnup is associated with at least one selected from the plurality of fission fuel subassemblies.   24. The method of claim 23, wherein the combustion wavefront standard includes a combustion wavefront position within at least one selected from the plurality of fission fuel subassemblies.   Determining a movement from a first position to a second position along a respective first dimension for a selection from the plurality of fission fuel subassemblies selected from the plurality of fission fuel subassemblies; 2. The method of claim 1, comprising determining a radial movement from a first position to a second position along each first dimension.   Determining a movement from a first position to a second position along a respective first dimension for a selection from the plurality of fission fuel subassemblies selected from the plurality of fission fuel subassemblies; The method of claim 1 comprising determining a helical movement from a first position to a second position along each first dimension.   Determining a movement from a first position to a second position along a respective first dimension for a selection from the plurality of fission fuel subassemblies selected from the plurality of fission fuel subassemblies; The method of claim 1 comprising determining axial translation for.   The desired shape of the combustion wavefront of the fission traveling wave is a substantially spherical shape, a shape that conforms to a selected continuous curved surface shape, a shape that is substantially rotationally symmetric with respect to the second dimension, and a shape with respect to the second dimension. The method of claim 1, comprising a shape selected from shapes that are substantially n-fold rotationally symmetric.   The method of claim 1, wherein the desired shape of the combustion wavefront of the fission traveling wave is asymmetric.   36. The method of claim 35, wherein the desired shape of the fission traveling wave combustion wavefront is rotationally asymmetric with respect to the second dimension. A fission traveling wave along the second dimension in a plurality of fission fuel subassemblies based on a selected set of dimensional constraints on the combustion wavefront of the fission traveling wave propagating along the first and second dimensions. A first electrical circuit configured to determine a desired shape of the combustion wavefront of
A selection from the plurality of nuclear fission fuel subassemblies is configured to determine movement from a first position to a second position along a respective first dimension to correspond to the desired shape. A system comprising: a second electrical circuit;   38. The system of claim 37, wherein the second electrical circuit is further configured to determine an existing shape of a combustion wavefront of the fission traveling wave.   The second electrical circuit is further configured from a first position along a respective first dimension to a second position to build the desired shape for a selection from the plurality of fission fuel subassemblies. 38. The system of claim 37, wherein the system is configured to determine movement.   The second electrical circuit is further configured from a first position along a respective first dimension to a second position to maintain the desired shape for a selected one of the plurality of fission fuel subassemblies. 38. The system of claim 37, wherein the system is configured to determine movement.   The second electrical circuit further moves each of the selected fission fuel subassemblies from a first position to a second position along a first dimension to correspond to the desired shape. 38. The system of claim 37, configured to determine when to do.   38. The system of claim 37, wherein the first dimension is substantially orthogonal to a major axis of the plurality of fission fuel subassemblies.   38. The system of claim 37, wherein the first dimension and the second dimension are substantially perpendicular to each other. 38. The system of claim 37, wherein the first dimension includes a radial dimension, and the second dimension includes an axial dimension. 38. The system of claim 37, wherein the first dimension includes an axial dimension, and the second dimension includes a radial dimension. 38. The system of claim 37, wherein the first dimension includes an axial dimension, and the second dimension includes a lateral dimension. 38. The system of claim 37, wherein the first dimension includes a lateral dimension and the second dimension includes an axial dimension. 38. The system of claim 37, wherein the first position includes an outer position and the second position includes an inner position. The inner position and the outer position are geometric approximations to the center of the reactor core, the neutron flux is such that the neutron flux at the inner position is larger than the neutron flux at the outer position, and the k _{effective at the} inner position is _49. The system of claim 48, based on at least one attribute selected from a reactivity that is greater than k _{effective at the} outer location. 38. The system of claim 37, wherein the first position includes an inner position and the second position includes an outer position. The inner position and the outer position are geometric approximations to the center of the reactor core, the neutron flux is such that the neutron flux at the inner position is larger than the neutron flux at the outer position, and the k _{effective at the} inner position is _51. The system of claim 50, based on at least one attribute selected from a reactivity that is greater than k _{effective at the} outer location.   38. The system of claim 37, wherein the first position and the second position are located on opposite sides of a reference value along the first dimension.   38. The system of claim 37, wherein the first location and the second location include at least one attribute that is substantially equalized.   54. The system of claim 53, wherein the at least one attribute comprises an attribute selected from a geometric approximation to a central region of the reactor core, neutron flux, and reactivity.   38. The system of claim 37, wherein the second electrical circuit is further configured to determine at least one rotation of a selection from the plurality of fission fuel subassemblies.   38. The system of claim 37, wherein the second electrical circuit is further configured to determine at least one inversion of a selection from the plurality of fission fuel subassemblies.   38. The system of claim 37, wherein the selected set of dimensional constraints includes a predetermined maximum distance along the second dimension.   38. The system of claim 37, wherein the selected set of dimensional constraints is a function of at least one combustion wavefront standard.   59. The system of claim 58, wherein the combustion wavefront standard includes a neutron flux.   60. The system of claim 59, wherein the neutron flux is associated with at least one selected from the plurality of fission fuel subassemblies.   59. The system of claim 58, wherein the combustion wavefront standard includes a neutron fluence.   64. The system of claim 61, wherein the neutron fluence is associated with at least one selected from the plurality of fission fuel subassemblies.   59. The system of claim 58, wherein the combustion wavefront standard includes burnup.   64. The system of claim 63, wherein the burnup is associated with at least one selected from the plurality of fission fuel subassemblies.   59. The system of claim 58, wherein the combustion wavefront standard includes a combustion wavefront location within at least one selected from the plurality of fission fuel subassemblies.   The second electrical circuit is further configured to determine a radial movement from a first position to a second position along a respective first dimension for a selection from the plurality of fission fuel subassemblies. 38. The system of claim 37, wherein:   The second electrical circuit is further configured to determine a helical movement from a first position to a second position along a respective first dimension for a selection from the plurality of fission fuel subassemblies. 38. The system of claim 37.   38. The system of claim 37, wherein the second electrical circuit is further configured to determine an axial translation for a selection from the plurality of fission fuel subassemblies.   The first electrical circuit further includes a substantially spherical shape, a shape adapted to a selected continuous curved surface, a shape that is substantially rotationally symmetric with respect to the second dimension, and a substantially n-fold rotational symmetry with respect to the second dimension. 38. The system of claim 37, configured to determine a shape of a combustion wavefront of the fission traveling wave selected from a shape that is   38. The system of claim 37, wherein the desired shape of the fission traveling wave combustion wavefront is asymmetric.   72. The system of claim 70, wherein the desired shape of the fission traveling wave combustion wavefront is rotationally asymmetric with respect to the second dimension. A fission traveling wave along the second dimension in a plurality of fission fuel subassemblies based on a selected set of dimensional constraints on the combustion wavefront of the fission traveling wave propagating along the first and second dimensions. First computer readable medium software program code configured to determine a desired shape of the combustion wavefront of
A selection from the plurality of nuclear fission fuel subassemblies is configured to determine movement from a first position to a second position along a respective first dimension to correspond to the desired shape. A computer software program product comprising: a second computer readable medium software program code.   73. The computer software program product of claim 72, wherein the second computer readable medium software program code is further configured to determine an existing shape of a combustion wavefront of the fission traveling wave.   The second computer readable medium software program code further includes a first position from a first location along a respective first dimension to build the desired shape for a selection from the plurality of fission fuel subassemblies. 73. The computer software program product of claim 72, configured to determine a move to a second position.   The second computer readable medium software program code further includes a first position along a respective first dimension so as to maintain the desired shape for one selected from the plurality of fission fuel subassemblies. 73. The computer software program product of claim 72, configured to determine a move to a second position.   The second computer readable media software program code is further selected from a first location along a first dimension to correspond to the desired shape for one selected from the plurality of fission fuel subassemblies. 73. The computer software program product of claim 72, configured to determine when to move to a second position.   73. The computer software program product of claim 72, wherein the first dimension is substantially orthogonal to a major axis of the plurality of fission fuel subassemblies.   The computer software program product of claim 72, wherein the first dimension and the second dimension are substantially perpendicular to each other. 73. The computer software program product of claim 72, wherein the first dimension includes a radial dimension and the second dimension includes an axial dimension. 73. The computer software program product of claim 72, wherein the first dimension includes an axial dimension, and the second dimension includes a radial dimension. 73. The computer software program product of claim 72, wherein the first dimension includes an axial dimension, and the second dimension includes a lateral dimension. 73. The computer software program product of claim 72, wherein the first dimension includes a lateral dimension, and the second dimension includes an axial dimension. 73. The computer software program product of claim 72, wherein the first location includes an outer location and the second location includes an inner location. The inner position and the outer position, the geometrical approximation to the central portion of the core of the reactor, the neutron flux in the inner position is greater than the neutron flux in the outer position, and k _Effective k _Effective is the outer position in the inside position 84. The computer software program product of claim 83, based on at least one attribute selected from a reactivity that is greater than. 73. The computer software program product of claim 72, wherein the first location includes an inner location and the second location includes an outer location. The inner position and the outer position are geometric approximations to the center of the reactor core, the neutron flux is such that the neutron flux at the inner position is larger than the neutron flux at the outer position, and the k _{effective at the} inner position is _86. The computer software program product of claim 85, based on at least one attribute selected from a reactivity that is greater than k _{effective at the} outer location.   The computer software program product of claim 72, wherein the first position and the second position are located on opposite sides of the reference value along the first dimension.   74. The computer software program product of claim 72, wherein the first location and the second location include at least one attribute that is substantially equalized.   90. The computer software program product of claim 88, wherein the at least one attribute comprises an attribute selected from a geometric approximation to a central region of the reactor core, a neutron flux, and a reactivity.   73. The computer software program product of claim 72, wherein the second electrical circuit is further configured to determine at least one rotation of a selection from the plurality of fission fuel subassemblies.   73. The computer software program product of claim 72, wherein the second electrical circuit is further configured to determine at least one inversion of a selection from the plurality of fission fuel subassemblies.   73. The computer software program product of claim 72, wherein the selected set of dimensional constraints includes a predetermined maximum distance along the second dimension.   74. The computer software program product of claim 72, wherein the selected set of dimensional constraints is a function of at least one combustion wavefront standard.   94. The computer software program product of claim 93, wherein the combustion wavefront standard includes a neutron flux.   95. The computer software program product of claim 94, wherein the neutron flux is associated with at least one selected from the plurality of fission fuel subassemblies.   94. The computer software program product of claim 93, wherein the combustion wavefront standard includes a neutron fluence.   99. The computer software program product of claim 96, wherein the neutron fluence is associated with at least one selected from the plurality of fission fuel subassemblies.   94. The computer software program product of claim 93, wherein the combustion wavefront standard includes burnup.   99. The computer software program product of claim 98, wherein the burnup is associated with at least one selected from the plurality of fission fuel subassemblies.   94. The computer software program product of claim 93, wherein the combustion wavefront standard includes a combustion wavefront position within at least one selected from the plurality of fission fuel subassemblies.   The second computer readable medium software program code is adapted to determine a radial movement from a first position to a second position along a respective first dimension for a selection from the plurality of fission fuel subassemblies. 75. The computer software program product of claim 72, comprising third computer readable medium software program code configured in   The second computer readable medium software program code is configured to determine a helical movement from a first position to a second position along a respective first dimension for a selection from the plurality of fission fuel subassemblies. 73. A computer software program product according to claim 72, wherein the computer software program product comprises a fourth computer readable medium software program code.   73. The second computer readable media software program code comprises fifth computer readable media software program code configured to determine an axial translation for a selection from the plurality of fission fuel subassemblies. A computer software program product as described in.   The first computer readable medium software program code has a substantially spherical shape, a shape that conforms to a selected continuous curved surface, a shape that is substantially rotationally symmetric with respect to the second dimension, and a substantially n-fold for the second dimension. 75. The computer software program product of claim 72, comprising sixth computer readable medium software program code configured to determine a shape selected from shapes that are rotationally symmetric.   74. The computer software program product of claim 72, wherein the desired shape of the combustion wavefront of the fission traveling wave is asymmetric.   106. The computer software program product of claim 105, wherein the desired shape of the combustion wavefront of the fission traveling wave is rotationally asymmetric with respect to the second dimension.

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