RU2562063C2 - Methods of moving fuel assemblies in fission nuclear reactor (versions) - Google Patents

Abstract

FIELD: physics, atomic power.

SUBSTANCE: invention relates to operation of travelling-wave reactors. A method of operating a reactor includes a step where the travelling wave burning front propagates along first and second dimensions in multiple fuel subassemblies in the reactor core, and a step where said subassemblies are controllably moved along a first direction, which determines the shape of the burning front. Controlled movement of the subassemblies along the first dimension is carried out radially and helically.

EFFECT: optimising the nuclear fuel burning mode and increasing the burn-out level thereof.

44 cl, 61 dwg

Description

FIELD OF THE INVENTION

The present invention relates to methods and systems for moving fuel assemblies in a nuclear fission reactor.

CROSS RELATIONS TO RELATED APPLICATIONS

This application relates (and claims benefits from them) to the earliest available valid date (s) for filing the following listed applications (hereinafter referred to as “Related Applications”) (for example, claims the earliest available priority dates for other patent applications, other than provisional, or claims benefits in accordance with 35 USC § 119 (e) for provisional patent applications, for any and all generic applications of the Related Application (Related Applications). ok Related Applications fully incorporated by reference into this description to the extent that this subject is consistent with this description.

Related Applications

For purposes not covered by the requirements of the USPTO, the present application is a partial continuation of US Patent Application No. 12/590448 entitled "METHODS AND SYSTEMS FOR MIGRATING FUEL ASSEMBLIES IN A NUCLEAR FISSION REACTOR" in which Ehud Greenspan , Roderick A. Hyde, Robert C. Petroski, Joshua C. Walter, Thomas Allan Weaver, Charles Whitmer, Lowell L. Wood, Jr., and George B. Zimmerman are named as inventors, filed November 6, 2009, which is currently is simultaneously considered,

or is an application simultaneously considered with which the application has the right to priority by filing date.

For purposes not covered by the USPTO, this application is a partial continuation of US Patent Application No. 12/657725 entitled "METHODS AND SYSTEMS FOR MIGRATING FUEL ASSEMBLIES IN A NUCLEAR FISSION REACTOR", in which Ehud Greenspan, Roderick A. Hyde, Robert C. Pelroski. C. Walter, Thomas Allan Weaver, Charles Whitmer, Lowell L. Wood, Jr., and George B. Zimmerman are named as inventors, filed January 25, 2010, which is currently being considered, or is the application being simultaneously considered. The application is entitled to priority on the filing date.

For purposes not covered by the USPTO, this application is a partial continuation of US Patent Application No. 12/657726 entitled "METIIODS AND SYSTEMS FOR MIGRATING FUEL ASSEMBLIES IN A NUCLEAR FISSION REACTOR" in which Ehud Greenspan, Roderick A. Hyde, Robert C. Petroski, Joshua C. Walter. Thomas Allan Weaver, Charles Whitmer. Lowell L. Wood. Jr., and George B. Zimmerman are named as inventors, filed January 25, 2010, which is currently being considered, or is an application that is simultaneously being considered, with which the application is entitled to priority by filing date.

For purposes not covered by the USPTO, this application is a partial continuation of US Patent Application No. 12/657735 entitled "METHODS AND SYSTEMS FOR MIGRATING FUEL ASSEMBLIES IN A NUCLEAR FISSION REACTOR", in which Ehud Greenspan, Roderick A. Hyde, Robert C. Petroski, Joshua C. Walter, Thomas Allan Weaver, Charles Whitmer. Lowell L. Wood. Jr., and George B. Zimmerman are named as inventors, filed January 25, 2010, which is currently being considered, or is an application that is simultaneously being considered, with which the application is entitled to priority by filing date.

The USPTO has published a notice that USPTO computer programs require applicants to reference the application serial number and indicate whether the application is a continuation, partial continuation or division of a patent application. See Stephen G. Kunin, Benefit of Prior-Filed Application, USPTO Official Gazette March 18, 2003. The current applicant entity (hereinafter referred to as the "Applicant") has provided the above-mentioned specific reference to the application (s) for which claims are claimed for priority, in accordance with the requirements of the law. The Applicant understands that the law is unambiguous in its specific conditional language and does not require the serial number of the application, or any description, for example, “continuation” or “partial continuation”, to claim priority over US patent applications. Notwithstanding the foregoing. The Applicant understands that the USPTO computer programs have certain data entry requirements, and therefore the Applicant has provided a designation (s) for the relationship between the current application and its generic application (s) indicated above (but), but positively notes that these designations should in no case be construed as any type of explanation and (or) assumption as to whether this application contains or does not contain any new material in addition to the material of its generic application ( ayavok).

SUMMARY OF THE INVENTION

Pa examples of illustrative embodiments of the proposed methods and systems for moving fuel assemblies in a nuclear fission reactor, methods of operating a nuclear reactor on a traveling wave, methods for controlling a nuclear reactor on a traveling wave, systems for controlling a nuclear reactor on a traveling wave, computer software products for controlling a nuclear reactor traveling wave and traveling wave nuclear reactors with systems for moving fuel assemblies.

The above brief description is merely illustrative and is not intended in any way to limit the scope of the present invention. In addition to the illustrative aspects, embodiment, and features described above, from the graphic material and the following detailed description, further aspects, embodiments, and features will become apparent.

BRIEF DESCRIPTION OF THE GRAPHICAL MATERIAL

1A is a flowchart of an illustrative method of operating a traveling wave nuclear reactor.

1B-1D are perspective views in partially schematic view of components of illustrative core areas of a nuclear reactor.

1E-1H illustrate the effects on the shape of the combustion front of a traveling wave of nuclear fission of the movement of selected nuclear fission fuel subassemblies.

FIG. 1I is a flowchart) detail of a part of the method of FIG. 1A.

1J illustrates the rotation of a nuclear fission fuel subassembly.

FIG. 1K is a flowchart of a detail of a part of the method of FIG. 1A.

Fig. 1L illustrates the inversion of a nuclear fission fuel subassembly.

1M-1N are flowcharts of a detail of a part of the method of FIG. 1A.

1O illustrates the helical movement of a nuclear fission fuel subassembly.

FIG. 1P is a flowchart of a detail of a part of the method of FIG. 1A.

Fig. 1Q illustrates axial movement of a nuclear fission fuel subassembly.

Fig. 1R illustrates the practically spherical shape of the combustion front of a traveling wave of nuclear fission.

Fig. 1S illustrates a continuously curved surface of a combustion front of a traveling nuclear fission wave.

Fig. 1T illustrates an almost axisymmetric shape of the combustion front of a traveling nuclear fission wave.

Figures 1U-IV illustrate practically n-fold axial symmetry of the shape of the combustion front of a traveling nuclear fission wave.

Fig. 1W illustrates the asymmetric shape of the combustion front of a traveling wave of nuclear fission.

1X-1AF are block diagrams of parts of parts of the method of FIG. 1A.

2A is a flowchart of an illustrative method for controlling a traveling policy nuclear reactor.

2B-2M are block diagrams of parts of parts of the method of FIG. 2A.

3A is a block diagram of an illustrative system for a system for determining the movement of nuclear fission fuel subassemblies.

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

Fig. 4A is a block diagram of an illustrative system for moving nuclear fission fuel subassemblies.

4B-4C are block diagrams of parts of system components in FIG. 4A.

5 is a block diagram in partially schematic view of an illustrative traveling wave nuclear reactor.

6A is a flowchart of an illustrative method of operating a traveling wave nuclear reactor.

6B is a flowchart of a detail of a part of the method of FIG. 6A.

7 is a flowchart of an illustrative method of operating a traveling wave nuclear reactor.

Fig. 8 is a flowchart of an illustrative method of operating a traveling wave nuclear reactor.

9 is a flowchart of an illustrative method of operating a traveling wave nuclear reactor.

10A is a flowchart of an illustrative method of operating a nuclear reactor.

10B-10D are block diagrams of parts of the parts of the method in FIG.

DETAILED DESCRIPTION

In the following detailed description, reference is made to the accompanying drawings. In these drawings, unless the context dictates otherwise, similar components are denoted by like numbers. The illustrative embodiments described in the detailed description, drawings, and claims are not to be construed as limiting the scope of the present invention. Other embodiments may be used, and other changes may be made within the spirit or scope of the subject matter presented in this application.

In accordance with illustrative embodiments, methods and systems are provided for moving fuel assemblies in a nuclear fission reactor, methods for operating a traveling wave nuclear reactor, methods for controlling a traveling wave nuclear reactor, systems for controlling a traveling wave nuclear reactor, computer control software products a traveling-wave nuclear reactor; and traveling-wave nuclear reactors with systems for moving fuel assemblies.

Overview of the traveling wave of nuclear fission

Before details will be explained regarding non-limiting embodiments, a brief overview will be given regarding a traveling nuclear fission wave. Although a traveling nuclear fission wave is also known as a deflagration nuclear fission wave, for clarity, the term “nuclear fission traveling wave” will be used in the present description. Parts of the subsequent review include information from a report entitled "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 , Roderic Hyde, and John Nuckolls, presented at a seminar in July 2003 at the Asppa Institute for Global Change, published by Livermoreka National Laboratory named after Lawrence (University of California) UCRL-JRNL-122708 (2003) (this paper was written as an article for Energy, International Journal on November 30, 2003), the contents of which are hereby incorporated by reference.

In the "wave", which moves through the active zone of a nuclear reactor on a traveling wave with speeds of the order of about a centimeter per year. The reproduction material of nuclear fuel is reproduced in the fissile material of nuclear fuel, which then undergoes fission.

Some of the nuclear fuels intended for use in traveling-wave nuclear reactors are usually widely available, such as (without limitation) uranium (natural, depleted or enriched), thorium, plutonium, or even previously burned fuel assemblies. Other less widely available nuclear fuels can be used, such as (without limitation) other actinide elements or their isotopes. Some traveling-wave nuclear reactors require long-term operation with full power for about 30-50 years or longer. Some traveling-wave nuclear reactors do not require refueling with nuclear fuel (instead, they assume a landfill at the end of their service life), and some other traveling-wave nuclear reactors involve refueling with nuclear fuel, with some refueling with nuclear fuel at a scheduled shutdown and some refueling nuclear fuel occur when working with energy generation. It is also assumed that in some cases, the regeneration of nuclear fuel can be avoided, thereby reducing the likelihood of military use and other problems.

The simultaneous fulfillment of desires to achieve exploitation of 30-50 years (or longer) at full capacity without refueling with nuclear fuel and to avoid the regeneration of nuclear fuel can entail the use of a spectrum of fast neutrons. In addition, the propagation of a traveling wave of nuclear fission provides a high average burnup of unenriched actinide fuels, such as natural uranium or thorium, and the use of a relatively small region of the “nuclear fission igniter” of moderate isotopic enrichment of nuclear fissile materials in the fuel charge of the reactor core.

As such, the active zone of a traveling-wave nuclear reactor may include a nuclear fission igniter and a larger propagation region of a deflagration nuclear fission combustion wave. The propagation region of a deflagration nuclear fission combustion wave contains thorium or uranium fuel and acts according to the general principle of nuclear fuel reproduction using a fast neutron spectrum.

The active zone of a traveling wave nuclear reactor is a breeder, but for the reasons for the efficient use of nuclear fuel and minimization of the need for isotope enrichment. In addition, the fast neutron spectrum is used because a large absorption cross section for fission products for thermal neutrons usually does not allow high utilization of thorium or a more abundant ²³⁸ U uranium in uranium fuel embodiments without removing fission products.

An illustrative traveling wave of nuclear fission will now be explained. Propagation of deflagration combustion waves through nuclear fuel materials can release energy at predicted levels. In addition, if the material configuration has enough time-independent features, for example, as the configurations found in typical industrial nuclear power reactors. then subsequent energy production may be at a sustainable level. Finally, if the speed of propagation of a traveling wave could be controlled from the outside in a practically justified way, then the rate of release of energy and, thus, energy production could be controlled as required.

The following explains the nucleonics of a traveling wave of nuclear fission. The induction of nuclear fission of selected isotopes of actinide elements fissile by the absorption of neutrons of any energy can ensure the release of binding energy of the nucleus at any temperature of the material, including arbitrarily low. Neutrons that are absorbed by a fissile actinide element can be created by a nuclear fission igniter.

The release of more than one neutron per absorbed neutron, on average, by nuclear fission of virtually any fissile actinide isogon can enable the divergence of neutron-mediated nuclear chain reaction. Usually, the number of neutrons released during each absorption is defined as η, where η = υσ _f / (σ _f + σ _c ), where υ is the number of neutrons released during fission. The release of more than two neutrons for each neutron absorbed (in certain ranges of neutron energy, on average) may first allow the conversion of an atom of a non-fissile isotope into a fissile (via neutron capture and subsequent beta decay) by initial neutron capture, and then further allow the neutron to divide the nucleus of the newly created fissile isotope during the second absorption of nuclear fission.

Many nuclear species with high Z (Z≥90) can be used as nuclear fuel material in a traveling wave reactor (or breeder reactor) if, on average, one neutron from a given nuclear fission event can be radioactively captured on a non-fissionable, but reproducing nucleus , which then turns (for example, by beta decay) into a fissile nucleus, and the second neutron from the same nuclear fission event can be captured on the fissile nucleus and, thereby, cause fission. In particular, if any of these conditions are established, the conditions for the propagation of a traveling wave of nuclear fission may be sufficient in this material.

Due to the beta decay of the intermediate isotopes in the process of converting the reproducing nucleus to fissile, the rate at which fissile material is made available for fission is limited. Therefore, the characteristic wave propagation velocity is limited by half-lives of the order of several days or months. For example, the characteristic velocity may be of the order of the distance traveled by a neutron from its birth during fission to its radiation capture on the reproducing nucleus (that is, the mean free path) to the half-period (the longest-lived nucleus in the chain) of beta decay resulting from the reproducing nucleus to fissile. For most cases of interest, this characteristic distance of neutron transport during fission in actinides of normal density is approximately 10 cm, and the half-life of beta decay is 10 ⁵ -10 ⁶ seconds. Accordingly, for some designs, the characteristic wave velocity is 10 ^-4 -10 ^-7 cm / s. Progress at this relatively low speed indicates that. that a wave can be characterized as a traveling or deflagration wave, but not a detonation wave.

If a traveling wave tries to accelerate its advancement, its leading edge collides with an increasingly pure reproducing material (which is relatively neutron-lossy material), since the concentration of fissile nuclei far in front of the center of the wave becomes exponentially low. Thus, the leading edge of the wave (referred to herein as the “combustion front”) stops or slows down the propagation. Conversely, if the wave slows down propagation and the conversion coefficient is maintained above unity (i.e., the reproduction rate is higher than the fission rate), the local concentration of fissile nuclei from ongoing beta decay increases, the local fission and production rates of neutrons increase, and the leading edge of the wave, then there is a combustion front, accelerating.

Finally, if the heat associated with nuclear fission is quickly removed, all parts of the configuration of the initially reproducing substance in which the wave propagates are removed, propagation can occur at an arbitrarily low material temperature - although the temperatures of both neutrons and fissioning nuclei can be about 1 MeV.

These conditions for the initiation and propagation of a traveling wave of nuclear fission can be achieved with readily available materials. Although fissile isotopes of actinide elements are rarely found in the earth's crust, both in absolute terms and in terms of reproducing isotopes of these elements, fissile isotopes can be concentrated, enriched and synthesized. For example, it is well known to use both natural and artificial fissile isotopes, such as ²³³ U, ²³⁵ U and ²³⁹ Pu, respectively, for initiating nuclear chain reactions.

An examination of the corresponding neutron cross section suggests that a traveling nuclear fission wave can burn most of the core from natural actinides, such as ²³² Th or ²³⁸ U, if the neutron spectrum in the wave is 'hard' or 'fast'. That is, if neutrons that carry a valuable reaction in the wave have energies that are not very small compared to about 1 MeV, at which they evaporate from the early fission fragments, relatively large losses for the space-time local neutron balance can be avoided, if the local mass fraction of fission products becomes comparable with the mass fraction of reproducing material (remembering that one mole of fissile material during fission turns into two moles of fission product nuclei). At neutron energies ≤0.1 MeV, neutron losses can become significant even in typical structural materials of neutron reactors, such as Ta, which has the required properties at high temperatures.

Another consideration is the (relatively small) change in the incident neutron energy of the multiplicity of neutrons emitted during fission, ν, and the fraction of all neutron absorption events that lead to fission (and not just emission of γ-rays upon neutron capture), α. The algebraic sign of the function α (ν-2) constitutes the condition for the feasibility of propagating a traveling nuclear fission wave in a reproducing material compared to the overall balance of the fissile isotope mass in the absence of neutron leakage from the core or spurious absorption (such as fission products) in it, for each of the fissile isotopes of the reactor core. The algebraic sign is usually positive for all fissile isotopes of interest from neutron energies by fission of approximately 1 MeV down to the region of resonance capture.

The quantity α (ν-2) / ν determines the upper limit of the fraction of all neutrons produced by fission, which can be lost due to leakage, spurious absorption, or geometric divergence during the propagation of a traveling wave. It should be noted that this fraction is 0.15-0.30 for the main fissile isotopes in the neutron energy range, which prevails in all configurations of effectively immediate actinide isotopes of practical interest (approximately 0.1-1.5 MeV). In contrast to the situation prevailing for neutrons (above) thermal energy, in which spurious losses due to fission products dominate spurious losses during conversion from a reproducing element into fissile by 1-1.5 decimal orders of magnitude, the generation of fissile elements during capture by reproducing isotopes exceeds capture of fission products by 0.7 1.5 orders of magnitude in the neutron energy range 0.1-1.5 MeV. The first assumes that the conversion from a reproducing element to a fissile one will be feasible only to the extent of 1.5-5% at or near the thermal energies of neutrons, while the latter indicates that transformations over 50% can be expected for the direct neutron neutron energy spectrum.

When considering the conditions for the propagation of a traveling nuclear fission wave for some approaches, neutron leakage for very large “self-reflected” actinide configurations can be effectively neglected. It is clear that the propagation of a traveling wave can be established in fairly large configurations of two types of actinides, which are relatively numerous in the earth's crust: ²³² Th and ²³⁸ U, the exceptional and main (that is, the most long-lived) isotopic components of natural thorium and uranium, respectively.

In particular, the fission neutron transport in these actinide isotopes is likely to lead either to capture of the reproducing isotope on the nucleus or to fission of the fissioning nucleus before the neutron energy decreases significantly below 0.1 MeV (and after which it becomes amenable - with no negligible probability of capture at the core of the fission product). It is clear that the concentration of fission product nuclei can approach or exceed the concentrations of reproducing nuclei in some cases, and the concentrations of fissile nuclei can be an order of magnitude lower than those of fission products or reproducing nuclei, while remaining quantitatively practically reliable. An examination of the corresponding neutron scattering cross sections suggests that configurations of actinides that are extensive enough to be effectively infinitely thick, that is, self-reflecting for fission neutrons in their radial size, will have density products with a radius of >> 200 g / cm ² - there, they will have radii >> 10-20 cm of a density of solid ²³⁸ U- ²³² Th.

A self-regulating wave (“Samoyed wave”) provides enough excess neutrons for the reproduction of a new fissile material of 1-2 medium free paths into an still full of fuel, effectively replacing the fissile fuel burned in the wave. The 'ash' behind the peak of the combustion wave is practically 'neutron-neutral', since the neutron reactivity of its fissile fraction is balanced by spurious absorption of the structure reserves and fission products at the top of the leak. If the supply of fissile atoms in the center of the wave and immediately in front of it does not change with time as the wave propagates, then this happens stably; if it’s less, then the wave “dies”, and if it’s more, they can say about the wave that it is “accelerating”.

Thus, a traveling wave of nuclear fission can propagate and be maintained practically in steady state for a long time in the configurations of isotopes of natural actinides.

In the above description, were considered, with an example not limiting the scope of the present invention, round cylinders of natural uranium or end metal with a diameter of less than about one meter (and which can be significantly smaller in diameter when using effective neutron reflectors) that can propagate traveling waves of nuclear fission to arbitrarily large axial distances. However, the propagation of traveling waves of nuclear fission should not be interpreted by confining circular cylinders, symmetric geometries or simply connected geometries. In this regard, further embodiments of alternative traveling-wave nuclear reactor core geometries are described in US Patent Application No. 11/605943 entitled "AUTOMATED NUCLEAR POWER REACTOR FOR LONG-TERM OPERATION)), in which RODERICK A.HYDE, MURIEL Y. ISIIIKAWA. NATHAN P.MYHRVOLD. AND LOWELL L.WOOD, JR. named as inventors, filed November 28, 2006, the contents of which are hereby incorporated by reference.

Propagation of a traveling wave of nuclear fission has implications for embodiments of traveling wave nuclear reactors. As a first example, feedback on the local temperature of the material in the traveling-wave neutron balance can be superimposed at a reasonable cost on the rate of a local nuclear reaction. This large negative temperature coefficient of neutron reactivity makes it possible to control the speed of propagation of a traveling wave. If only very small thermal energy is extracted from the burning fuel, its temperature rises, and the temperature-dependent reactivity decreases, and the nuclear fission rate in the center of the wave becomes correspondingly small, and the wave time equation reflects only a very low axial progression speed. Similarly, if the rate of thermal energy extraction is high, the temperature of the material decreases, and the neutron reactivity rises, the intra-wave neutron balance becomes relatively undamped, and the wave moves in the axial direction relatively quickly. Details regarding illustrative temperature feedback implementations that may be included in reactor core assembly embodiments are described in US Patent Application No. 11/605933 entitled "CONTROLEABLE LONG GEKM OPERATION OF A NUCLEAR REACTOR)), in which RODERICK A.HYDE , MURIEL Y. ISUIKAWA, NATHAN P.MYHRVOLD. AND LOWELL L. WOOD, JR .. are named as inventors, filed November 28, 2006, the contents of which are hereby incorporated by reference.

As a second example of the consequences of the propagation of a traveling wave of nuclear fission for embodiments of nuclear traveling wave reactors, less than all neutron production in fission in a traveling wave nuclear reactor can be used. For example, reactivity control systems, such as (without limitation) neutron-absorbing material in control rods or local modules that thermostat the temperature of the material, can use about 5-10% of the total neutron production in fission in a nuclear reactor 10 on a traveling wave. An additional ≤10% of the total neutron production during fission in a traveling wave nuclear reactor can be lost by parasitic absorption in highly efficient heat-resistant structural materials (such as Ta, W or Re) used in structural elements of a traveling wave nuclear reactor. This loss occurs in order to realize the required thermodynamic efficiency when converting to electrical energy and to achieve high system safety. Z of these materials, such as Ta, W and Re, are approximately 80% of Z of actinides, and thus their cross sections for radiation capture for high energy neutrons are not particularly small compared to their cross sections for radiation capture of actinides. The last 5–10% of the total neutron production during fission in a traveling wave nuclear reactor can be lost to spurious absorption in fission products. However, one can expect that the spectrum can be similar to the spectrum of a fast-neutron reactor cooled with liquid sodium in that parasitic absorption can account for only about 1-2% of the losses. As already noted, the neutron balance is characteristically rich enough that approximately 70% of the total neutron production in fission is sufficient to maintain the propagation of a traveling wave in the absence of leakage and rapid geometric divergence.

As a third example of the consequences of the propagation of a traveling wave of nuclear fission for embodiments of nuclear traveling wave reactors, high burnups (of the order of about 20-30%, or in some cases from about 40% or 50% to about 80%) of the initial stocks of actinide fuel, typical for traveling waves of nuclear fission, can provide highly efficient use of unenriched fuel, in addition, without the need for regeneration.

It should be noted that the neutron flux from the most intensely burning region behind the combustion front reproduces the region rich in fissile isotopes at the leading edge of the combustion front, thereby serving to advance the traveling wave of nuclear fission. After the combustion front of the traveling wave of nuclear fission passes over a given mass of fuel, the concentration of fissile atoms continues to increase, while the radiation capture of neutrons on existing reproducing nuclei is much more likely than on the nuclei of fission products, while continued fission will create an increasing mass of fission products . The density of nuclear energy production in this area of fuel charge at any given time is maximum.

It is clear that far behind the advancing combustion front of a traveling wave of nuclear fission, the ratio of the concentration of fission product nuclei (the mass of which on average is almost exactly equal to half the mass of the fissile nucleus) and fissile nuclei increases to a value comparable to the ratio of active fission to the cross sections for radiation capture of fission products. In this case, the "local neutron reactivity" approaches a negative value or (in some embodiments) may become negative. Consequently, combustion and reproduction effectively stop. It is also appreciated that in some embodiments, non-fissile neutron-absorbing material, such as boron carbide, hafnium or gadolinium, may be added to ensure that "local neutron reactivity" is negative.

In some embodiments of a traveling wave nuclear reactor, all of the nuclear fuel ever used in the reactor is installed in the manufacture of the reactor core assembly. In addition, in some designs, spent fuel is never removed from the reactor core assembly. In one approach, these options for implementation can ensure operation without access to the reactor core after the start of nuclear fission, possibly after completion of the propagation of the combustion front.

In some other traveling wave nuclear reactor embodiments, all nuclear fuel ever used in a reactor is installed in the manufacture of the reactor core assembly, and in some embodiments, spent fuel is never removed from the reactor core assembly. However, and as will be explained below, but at least some of the nuclear fuel can be moved or pulled between or among different places in the reactor core. This movement or dragging, but at least a portion of the nuclear fuel can be performed to achieve the goals, as described below.

However, in some other embodiments of a traveling wave reactor after the start of nuclear fission, additional nuclear fuel may be added to the reactor core assembly. In some other traveling wave nuclear reactor embodiments, spent fuel may be removed from the reactor core assembly (and, in some embodiments, spent fuel removal from the reactor core assembly may be performed when the traveling wave nuclear reactor is in power generation mode) . This illustrative nuclear refueling and spent fuel removal is explained in US Patent Application No. 11/605848 entitled "METHOD AND SYSTEM FOR PROVIDING FUEL IN A NUCLEAR REACTOR)), in which RODERICK A.HYDE, MURIEL Y.ISHIKAWA, NATHAN P. MYHRVOLD, AND LOWELL L.WOOD. Jr. named as inventors filed November 28, 2006. the contents of which are hereby incorporated by reference. Regardless of whether spent fuel or peg is removed, pre-expansion of the loaded fuel allows higher actinides to be replaced by lower density fission products without any general volumetric changes in the fuel cells as the traveling nuclear fission wave travels along any given axial element of actinide 'fuel', turning it into 'ash' - fission product

In general, the triggering of nuclear fission traveling waves in fuel loads of ²³² Th or ²³⁸ U can be initiated by nuclear fission igniter modules, such as, without limitation, fuel assemblies enriched in fissile isotopes. Illustrative nuclear fission igniter modules and methods for triggering traveling nuclear fission waves are described in detail in the co-pending US patent application No. 12/069908, entitled "NUCLEAR FISSION IGNITER", in which CHARLES E.AIILFELD, JOHN ROGERS GILLELAND, RODERICK A.HYDE, MURIEL Y.ISHIKAWA, DAVID G. MCALEES, NATHAN P. MYHRVOLD, CHARLES WHITMER, AND LOWELL L.WOOD, JR., Are named as inventors, filed February 12, 2008, the contents of which are hereby incorporated by reference. Higher enrichments can result in more compact modules, and minimum mass modules can use moderator concentration gradients. In addition, the design of nuclear fission igniter modules can be determined in part by non-technical considerations, such as resistance to the use of materials for military purposes in various scenarios.

In other approaches, illustrative nuclear fission ignitors may have other types of reactivity sources. For example, other nuclear fission igniters include “burning coals,” for example, nuclear fuel enriched in fissile isotopes when neutrons in a nuclear reactor travel on a traveling wave. These “burning coals” can act as nuclear fission igniters despite the presence of different amounts of fission products (“ashes”). In other approaches to launch a nuclear fission traveling wave, nuclear fission igniter modules enriched in fissile isogons can be used to complement other neutron sources that use electrically driven sources of high energy ions (such as protons, deuterons, alpha particles, etc.) or electrons, which in turn can produce neutrons. in an illustrative approach, a particle accelerator, such as a linear accelerator, may be provided to supply high energy protons to an intermediate material, which in turn can produce these neutrons (for example, by fission). In another illustrative approach, a particle accelerator, such as a linear accelerator, to feed high-energy electrons into the intermediate material, which in turn can produce these neutrons (for example, by electrodividing and (or) photo-sharing of elements with high m Z). Alternatively, neutrons can be produced by other known neutron-emitting processes and devices, such as in approaches with electrically induced fission (for example, 14 MeV neutrons from deuterium-tritium synthesis), and can be used in addition to nuclear fission igniter modules enriched in fissile isogons, to initiate the propagation of a fission wave.

Now, after considering the nucleonics of the fuel charge and the traveling wave of nuclear fission, further details will be considered regarding the “firing of the fission reaction” and the maintenance of the traveling wave of nuclear fission. A centrally located illustrative nuclear fission igniter moderately enriched in fissile material, such as ²³⁵ U or ²³⁹ Pu, has a neutron-absorbing material (such as borohybrid or the like) removed from it (for example, by electrical heating at the command of an operator or by extraction one or more control rods), and the nuclear fission igniter becomes neutron critical. The local temperature of the fuel rises to a predetermined temperature, and then is regulated, for example, by the reactor coolant system and (or) the reactivity control system or local thermostatic modules (which is described in detail in US patent application No. 11/605943 under the name "AUTOMATED NUCLEAR POWER REACTOR FOR LONG- TERM OPERATION)), in which RODERICK A.HYDE, MURIEL Y.ISHIKAWA, NATHAN P.MYHRVOLD, AND LOWELL L.WOOD, JR. named as inventors, filed November 28, 2006, the contents of which are hereby incorporated by reference). The fission neutrons due to the action of fast neutrons ²³⁸ U or ²³² Pu are captured mainly at the local ²³⁸ U or ²³² Th first.

It is clear that the uranium enrichment of a nuclear fission igniter can be reduced to levels not much higher than in the case of fuel for a light water nuclear reactor (LWR) by introducing into the igniter a nuclear fission and the fuel region directly surrounding it with a radial density gradient of a refractory moderator, such like graphite. The high density of the moderator allows poorly enriched fuel to satisfactorily burn out, and a decrease in the density of the moderator ensures efficient reproduction of fissile material. Thus, an optimal nuclear fission igniter design may include a trade-off between propagation stability and minimal latency from initial criticality to full rated power from a fully ignited core fuel load. The lower enrichment of the nuclear fission igniter will entail more reproducing generations and thus impose longer latencies.

In some embodiments, the peak reactivity of the reactor core assembly in the first stage of the firing reaction of the fission reaction may slowly decrease, because although the total number of fissile isotopes increases, this total number becomes more spatially dispersed. As a result of choosing the initial geometry of the fuel, enriching the fuel depending on the position and density of the fuel, it can be positioned for maximum reactivity, but in order to still be slightly positive at the point in time at which the minimum value is reached. Soon after, the maximum reactivity begins to increase rapidly to its highest value, corresponding to the total number of fissile isotopes in the reproduction area, significantly exceeding their total number remaining in the nuclear fission igniter. For many cases, the quasispherical annular shell then provides maximum specific energy production. At this point in time, the fuel load of the reactor core assembly may be referred to as “ignited”.

Now we will consider the propagation of a traveling wave of nuclear fission, which in the text of the present description may also be referred to as "burning of nuclear fuel." In the previously described embodiment, a spherically diverging shell with a maximum specific production of nuclear energy continues to move in the radial direction from the nuclear fission igniter to the outer surface of the fuel charge. Reaching the outer surface, it is usually divided into two spherical zonal surfaces, with each surface extending in the corresponding one of two opposite directions along the axis of the cylinder. At this point in time, the full potential of heat production can develop. This interval is characterized as such by the period of the start of the combustion fronts of two traveling propagating waves of nuclear fission propagating in the axial direction. In some embodiments, the core of the core fuel is ignited and two waves are generated, propagating in opposite directions. Such a design doubles the mass and volume of the core in which energy production occurs at any given moment, and thus halves the peak specific energy production of the core, thereby minimizing quantitatively the transfer problems for thermal neutrons. However, in other embodiments, the core fuel loading is ignited at or near one end, as required for a particular application. Such an approach can result in a single propagating wave in some designs.

In other embodiments, the core fuel loading may be ignited in several places. In still other embodiments, the core fuel loading is ignited at any three-dimensional location in the core, as required for a particular application. In some embodiments, two propagating traveling nuclear fission waves may be initiated and propagated away from the site of firing the fission reaction; however, depending on the geometry, composition of the nuclear fuel, or for other reasons, the action of the neutron-modifying control structure, different quantities (for example, one, three or more) of traveling fission waves can be initiated and propagated. However, for understanding and brevity, consideration in the text of the present description refers (without limitation) to the propagation of the combustion fronts of two traveling nuclear fission waves.

From this moment onwards, by breaking up two waves, when they reach two opposite ends or approach them, the physics of nuclear energy production is usually effectively constant in time within any wave. The speed of wave propagation through the fuel is proportional to the local neutron flux, which in turn linearly depends on the thermal energy extracted from the reactor core assembly by the combined action of the traveling wave of the neutron control system on the neutron balance. In one approach, a neutron control system may be implemented with thermostatic modules (not shown), as described in US Patent Application No. 11/605933 entitled "CONTROLLABLE LONG TERM OPERATION OF A NUCLEAR REACTOR", in which RODERICK A. HYDE, MURIEL Y. ISHIKAWA, NATHAN P. MYHRVOLD, AND LOWELL L.WOOD, JR. named as inventors, filed November 28, 2006, the contents of which are hereby incorporated by reference. In other approaches, the neutron control system can be implemented with one or more rods containing neutron-absorbing material and moved by one or more drive mechanisms of the control rods.

If a higher power is required from the reactor by means of a low-temperature coolant flowing into the core, in some embodiments, the temperature of the two ends of the core (which, in some embodiments, are closest to the coolant inlet openings) decreases slightly below the calculated setting of thermostatic modules, while the neutron absorber is drawn from the corresponding subpopulation of thermostatic core modules, and the local neutron flux is allowed to At the same time increase to bring the local production of thermal energy to a level that brings the local temperature of the material to the setting of the local thermostatic modules. In some other embodiments, temperature control may be performed by shimming control rods, as required in response to changes in controlled temperature.

However, in the embodiment with two combustion fronts, this process is inefficient in terms of significant heating of the coolant, while its two separated streams move into two nuclear combustion fronts. These two parts of the core fuel load, which can produce significant levels of atomic energy if not suppressed by neutron absorbers, then act to heat the coolant to the temperature indicated by the design setting of their modules, provided that the temperature of the nuclear fuel does not become excessive (and regardless of temperature at which the coolant has arrived in the core). Then, two coolant flows move through two sections of already burned fuel to the center of two combustion fronts, removing residual nuclear fission from them and removing residual heat in the existing fuel loading in its middle. This design contributes to the spread of two combustion fronts towards the two ends of the fuel loading by " trimming 'excess neutrons, mainly from the trailing edge of each front.

Thus, core neutronics in this design can be considered practically self-regulating. For example, for embodiments with a cylindrical core, core nucleonics can be considered practically self-regulating if the product of the fuel density and the radius of the cylindrical core is ≥200 g / cm ² (i.e., 1-2 average free paths for neutron-induced fission in a typical core composition, for a spectrum of moderately fast neutrons). One function of a neutron reflector in such a core design may be to significantly reduce the integral flux density (fluence) of fast neutrons observed in the outer parts of the reactor, such as its radiation shield, structural supports, outer shell and components of the reactivity control system, such as (without limitation) control rods (if provided) or thermostatic modules (if provided). In addition, the neutron reflector can affect the operation of the core by increasing the efficiency of reproduction and specific energy in the outer parts of the fuel. ^d ) that influence can increase the profitability of the reactor. The peripheral parts of the fuel charge are not used at low overall energy efficiency, but they have isotope burnout levels comparable to burnout levels in the middle of the fuel load.

Although core neutronics in this design can be considered practically self-regulating, other designs can operate under the control of a reactor control system that contains a corresponding electronic controller having an appropriate electrical circuit and which can contain an appropriate electromechanical system, such as one or more rods containing neutron-absorbing material and moved by one or more drive mechanisms of the control ster it.

Finally, irreversible cancellation of the neutron reactivity of the core can be carried out at any time by introducing a neutron absorber into the coolant flow, as required. For example, a light load of the coolant flow with a material such as BF ₃ , possibly simultaneously with a volatile reducing agent, such as H ₂ , if required, can lead to the deposition of metal boron almost uniformly on the inner walls of the coolant pipes passing through the reactor core, due to the exponential acceleration of the otherwise slow chemical reaction 2BF ₃ + 3H ₂ -> 2B + 6HF by the high temperatures that arise in drink. Boron, in turn, is a highly refractory metalloid and will usually not migrate from its deposition site. The almost uniform presence of boron in the core in quantities <100 kg can negate the reactivity of the neutrons in the core for an indefinitely long time without involving the use of drive mechanisms near the reactor.

In a general sense, specialists will understand that the various aspects described in this document, which can be implemented separately and (or) together by a variety of hardware, types of software, software and hardware, and (or) any combination of them, can be considered as consisting of the various types of "electrical circuits", Therefore, in the sense in which it is used in the present description, the term "electrical circuits" includes, without limitation, electrical circuits having at least one disk a retro electric circuit, electric circuits having at least one integrated circuit, electric circuits having at least one specialized integrated circuit, electric circuits forming a universal computing device configured by a computer program (e.g., a universal computer configured by a computer program which, at least partially carries out the processes and (or) devices described in this document, or a microprocessor configured by a computer a black program that at least partially implements the processes and (or) devices described in this document), electrical circuits forming a storage device (for example, types of memory (for example, random access memory, flash memory, read-only memory, etc.) .d.)), and (or) electrical circuits forming a communication device (for example, a modem, a communication switch (switch). optoelectric equipment, etc.). Those skilled in the art will understand that the subject matter described herein may be implemented in analog or digital form or in some combination thereof.

In a general sense, those skilled in the art will understand that the various aspects described herein that can be implemented separately and / or jointly by various types of electromechanical systems having a variety of electrical components, such as hardware, software, firmware, and (or) almost any combination of them; and a variety of components that can apply mechanical force or impart movement, such as rigid bodies, spring or torsion bodies, hydraulic devices, devices with an electromagnetic drive and (or) almost any combination of them. Therefore, in the sense in which it is used in the present description, the term "electromechanical system" includes, without limitation, electrical circuits functionally connected to the transducer (for example, an actuator, an electric motor, a piezoelectric crystal, a microelectromechanical system (MEMS), etc. ) electrical circuits having at least one discrete electrical circuit, electrical circuits having at least one integrated circuit, electrical circuits having at least one specialized integrated circuit, electrical circuits forming a universal computing device configured by a computer program (e.g., universal A computer configured by a computer program that at least partially implements the processes and / or devices described in this document ment, or microprocessor, configured by a computer program that at least partially implements the processes and (or) devices described herein), electrical circuits forming a storage device (for example, types of memory (for example, random access memory, flash memory , read-only memory, etc.)), electrical circuits forming a communication device (e.g., modem, communication switch (switch), optoelectric equipment, etc.) and (or) any non-electric analogue thereof, e.g., optical or other analogues. Professionals will also understand that examples of an electromechanical system include, without limitation, a wide variety of household electronic equipment systems, medical devices, as well as other systems such as automobile transport systems, factory automation systems, security systems and / or communication / computing systems. Those skilled in the art will understand that, unless the context may dictate otherwise, the term “electromechanical”, as used in the present description, is not necessarily limited to a system having both an electric and a mechanical drive.

Illustrative Embodiments

Now, after a brief overview is given regarding the initiation and propagation of a traveling nuclear fission wave, illustrative embodiments will be explained with examples not limiting the scope of the present invention.

The following is a series of flowcharts illustrating embodiments of the present invention. For ease of understanding, the flowcharts are structured and presented in such a way that the initial flowcharts represent embodiments by means of an exemplary embodiment, and then the subsequent flowcharts represent alternative embodiments and / or extensions of the initial flowchart (flowcharts) either as a subcomponent or as an additional component in relation to one or more block diagrams shown in one or more of the previously mentioned block diagrams. Those skilled in the art will understand that the presentation style used in the present description (for example, starting with presenting a flowchart (s) representing (representing) an exemplary (s) implementation (s), and then providing additions and (or) further details in the following flowcharts) typically provides a quick and easy understanding of the various process embodiments. In addition, specialists will understand that the presentation style used in the present description is still well suited to the paradigms of modular and (or) object-oriented programming.

Turning now to FIG. 1A, an illustrative method 10 for operating a traveling wave nuclear reactor is given as a general view. Turning further to FIG. 1B, which, by way of example, not limiting the scope of the present invention, illustrates components of an illustrative traveling-wave nuclear reactor 12. In the assembly 16 of the reactor core are located fuel subassemblies 14 nuclear fission. For clarity, FIG. 1B may illustrate less than all nuclear fission fuel subassemblies 14 that can be accommodated in reactor core assembly 16 embodiments.

In assembly 16 of the reactor core, a coordinate system is defined. In some embodiments, the coordinate system may be determined by an x-dimension, a y-dimension, and a z-dimension. In some other embodiments, the coordinate system may be determined whole by a radial dimension and an axial dimension. In some other embodiments, the coordinate system may include an axial dimension and a lateral dimension.

In some embodiments, the nuclear fission fuel assemblies 14 may be separate nuclear fuel elements such as rods, plates, spheres, and the like. nuclear fuel. In some other embodiments, the nuclear fission fuel subassemblies 14 may be nuclear fission fuel assemblies, that is, two or more separate nuclear fuel elements grouped into an assembly. Whatever the embodiment of the nuclear fission fuel subassemblies 14, the nuclear fuel material contained in the nuclear fission fuel subassemblies 14 may be any suitable type of nuclear fuel material, as described above.

As a general idea, the application of method 10 begins with block 18. In block 20, the front of burning of a traveling nuclear fission wave propagates (as shown by arrows 24) in the first and second dimensions in the fuel fission subassemblies 14 of the nuclear fission in the assembly 16 of the nuclear core 12 traveling wave reactor. In block 26, the selected nuclear fission subassemblies 14 are controllably moved to the first dimension from the corresponding first places to the corresponding second places so as to determine the shape of the combustion front of the traveling nuclear fission wave in the second dimension in accordance with the selected set of dimensional constraints. Method 10 is stopped at block 28.

Now, with examples not limiting the scope of the present invention, some illustrative details will be explained.

The fuel subassemblies 14 of nuclear fission carry a spatial relationship with the dimensions designated as the first and second dimensions. For example, in some embodiments, the nuclear fission fuel assemblies 14 may be elongated along the second dimension. In some embodiments, the second dimension may be a y-dimension or an axial dimension. In some other embodiments, the second measurement may be x-measurement, z-measurement, or side measurement.

In addition, in some embodiments, the first measurement may be substantially orthogonal to the elongated axis of the nuclear fission subassemblies 14. In some embodiments, the first dimension and the second dimension may be substantially orthogonal to each other.

As the first dimension and the second dimension, different dimensions can be designated. For example, in some embodiments, the first dimension may be a radial dimension, and the second dimension may be an axial dimension. In some other embodiments, the first dimension may be an axial dimension, and the second dimension may be a radial dimension. In some embodiments, the first dimension may be an axial dimension, and the second dimension may be a lateral dimension. In some other embodiments, the first dimension may be a lateral dimension, and the second dimension may be an axial dimension. In a cylindrical core with assemblies elongated in the axial direction, such as in typical configurations of industrial light water nuclear reactors, the first measurement may be a radial measurement and the second measurement may be an axial measurement. In other reactor configurations, such as the CANDU heavy water nuclear reactor configuration, the fuel assemblies are elongated in the first dimension and can be moved in a lateral or radial second dimension.

As shown in FIG. 1B, locations in the reactor core 12 according to various attributes may be characterized as first places and second places. Typically, a site can be considered as a space near the core region 12 of a nuclear fission fuel assembly 14. In addition, the place can be considered in general as the space directly surrounding any given zone in the reactor core 12, or can be considered as a large part of the reactor core 12. For example, if we turn to FIG. 1C, in some embodiments, the first places may be outwardly directed places 30, and the second places may be inwardly directed

locations 32. As shown in FIG. 1C, in some embodiments, inwardly located locations 32 and outwardly located locations 30 may be based on geometric proximity to the central portion of the reactor core 12. In some other embodiments, the implementation of inwardly directed places and outwardly directed places can be based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places. In some other embodiments, the implementation of inwardly directed places and outwardly directed places may be based on reactivity such that k _effective in inwardly directed places is higher than k _effective in outwardly oriented places. Embodiments typical of a traveling wave reactor may have outwardly directed places, including places outside or in the direction of the propagating wave, and inwardly directed places may include places through which the traveling nuclear fission wave propagates or has already spread.

Consider further examples, if we turn in addition to fig.1D. In some embodiments, the first locations may include inwardly extending locations 32, and the second locations may include outwardly extending locations 30. As shown in FIG. 1D, in some embodiments, the implementation of inwardly extending locations 32 and outwardly extending locations 30 may be based on geometric proximity to a central parts of the reactor core 12. In some other embodiments, the implementation of inwardly directed places and outwardly directed places can be based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places. In some other embodiments, the implementation of inwardly directed places and outwardly directed places may be based on reactivity as such. that k _effective in inwardly directed places above k _effective in outwardly directed places. In other embodiments, the implementation of the directed inward and outwardly places can be described in terms of the predominant nuclear reaction occurring in the - quiet areas. As an example, not limiting the scope of the present invention, an inwardly directed site may be characterized by predominant nuclear fission reactions, while an outwardly directed site may be characterized by predominant nuclear absorption reactions on the reproducing material.

Regardless of the characterization of first places and second places, as well as inwardly directed places or outwardly directed places, first places and second places may be characterized according to these attributes. For example, in some embodiments, the first places and second places may be on opposite sides of the initial value in the first dimension. In some other embodiments, the implementation of the first places and second places may include at least one attribute, practically equalized. For example, at least one attribute, which is practically equalized, may contain geometric proximity to the central region of the reactor core, neutron flux, reactivity, etc.

As one non-limiting example of the invention shown in FIG. 1E, selected nuclear fission fuel subassemblies (not shown for clarity) can be controlled to radially outward travel from respective inwardly directed locations 32 toward corresponding outwardly oriented locations 30 so as to determine the shape the front 22 of the combustion of a traveling wave of nuclear fission in the axial direction in accordance with the selected set of dimensional restrictions. As an illustration, and not as limiting the scope of the present invention, axial changes in the shape of the combustion front of a traveling nuclear fission wave 22 during radial movement of the nuclear fission fuel assemblies (not shown) are shown. The left figure illustrates the initial shape of the combustion front 22 of a traveling wave of nuclear fission. It is clear that for illustrative purposes only a quarter of the perimeter of the combustion front 22 of the traveling wave of nuclear fission is shown.

In the figure in the center, the selected nuclear fission fuel subassembly (not shown) was radially moved from the inwardly directed location 32 to the outward directed location 30 after the selected nuclear fission fuel assembly (not shown) burned for the required time or in accordance with the required reactivity parameter (such as, without limitation, burnout). The reactivity moved radially outward from the peak, which was radially located in the inwardly directed position 32 (as shown in the left figure), in the outwardly directed place 30 (as shown in the center figure).

Over the life of a traveling wave core 12 of a nuclear reactor, additional nuclear fission fuel subassemblies (not shown) can radially rearrange outward from inward points 32 to outward places 30. As a result of this additional outward directed movement, the nuclear fission fuel subassemblies (not shown) in places radially directed inward in the active zone 12 of a nuclear reactor on a traveling wave they can be kept from burning more than fuel assemblies nuclear fission (not shown) in radially outward places in the active zone 12 of a traveling wave nuclear reactor. As shown in the right figure, if a sufficient number of nuclear fission fuel subassemblies are moved radially outward, as described above, then the shape of the combustion front 22 of the traveling nuclear fission wave can approximate the Bessel function (cylindrical function). In addition, if a sufficient number of nuclear fission fuel subassemblies are moved radially outward, as described above, then all or almost all of the nuclear fission fuel subassemblies in the active zone 12 of the traveling wave nuclear reactor can reach their respective burnup limits or approach them almost simultaneously. And in this case, the use of nuclear fission fuel subassemblies in the active zone 12 of a traveling wave nuclear reactor is maximized

As another non-limiting example of the invention shown in FIG. 1F, the selected nuclear fission fuel assemblies 14 can be controlled to radially outwardly move from the respective inwardly directed locations 32 toward the corresponding outwardly directed locations 30, and other nuclear fission fuel assemblies 14 ′ it is possible to controllably “sweep” radially inward from the corresponding outwardly directed places 30 to the side of the corresponding inwardly directed places 32 so as to determine the shape of the front 22 axiom of a traveling wave of nuclear fission in the axial direction in accordance with the selected set of dimensional restrictions. That is, the selected nuclear fission fuel assemblies 14 and 14 ′ are interchanged between inwardly directed locations 32 and outwardly directed locations 30.

As an illustration and not as a limitation of the scope of the present invention, axial changes in the shape of the burning front of a nuclear fission traveling wave 22 are shown with interchangeable radial movement of the nuclear fission fuel assemblies 14 and 14 '. The left figure illustrates the initial shape of the combustion front 22 of a traveling wave of nuclear fission. In the left figure, the nuclear fission fuel assemblies 14 have more fissile content than the nuclear fission fuel assemblies 14 ′. For example, nuclear fission fuel subassemblies 14 may be part of an igniter assembly for a traveling wave nuclear reactor 12. As another example, nuclear fission assemblies 14 may comprise fissile material obtained from a reproducing isotopic material as a result of the absorption of fast neutrons in the active zone 12 of a traveling wave nuclear reactor and subsequent nuclear conversion into fissile isotopes. In contrast, nuclear fission fuel subassemblies 14 ′ have less fissile content than nuclear fission fuel assemblies 14. In some cases, the nuclear fission fuel subassemblies 14 ′ may contain more reproducing isotopic contents than the nuclear fission fuel subassemblies 14. In such cases, the nuclear fission fuel subassemblies 14 ′ are more absorbent for fast neutrons than the nuclear fission fuel subassemblies 14

In the right figure, the selected nuclear fission subassembly 14 was moved radially outward from the inwardly directed place 32 to the outwardly directed place 30, and the selected nuclear fission subassembly 14 'was moved radially inward from the outward directed 30 to the inwardly directed place 32. After exchanging the places of the fuel subassembly 14 and 14 'nuclear fission, the axial profile of the front of combustion 22 of the traveling wave of nuclear fission made more compact and more uniform than the axial profile of the front of 22 mountains Nia traveling wave nuclear fission before swapping (see. the left drawing). As a result, in some embodiments, for a combustion front 22 of a traveling wave of nuclear fission, a substantially uniform or uniform profile can be achieved. In some other embodiments, achieving a substantially uniform or uniform profile for the combustion front 22 of a traveling nuclear fission wave may not be required. In these cases, you may just need to move fissile material or move reproductive isotopic material. In some other embodiments, it may be necessary to expand the combustion front 22 of the traveling nuclear fission traveling wave in the radial dimension.

Turning further to FIG. The shape of the burning front of the nuclear fission traveling wave can also be determined in the radial dimension by moving the fuel fission subassemblies 14 and 14 ′ in the radial dimension, as discussed above with reference to FIG. 1F. The radial profile of the combustion front 22 of the traveling wave of nuclear fission can be considered as representing the neutron leakage current. The left and right figures of FIG. 1G show views along the axial dimension corresponding to the left and right figures, respectively, of FIG. 1F.

Turning now to FIG. 1H. The selected nuclear fission fuel assemblies 14 can be controlled laterally from the respective first places to the respective second places in order to determine the shape of the combustion front 22 of the traveling nuclear fission wave in the radial direction in accordance with the selected set of dimensional restrictions.

The left figure illustrates the initial shape of the combustion front 22 of the traveling wave of nuclear fission, when viewed in axial dimension. The selected nuclear fission fuel assembly 14 is located in the first place z, r, φ ₁ . In this example, shown for illustrative purposes, the nuclear fission fuel assembly 14 introduces reactivity in the first place z, r, φ ₁ , which can be determined (for any reason) in excess of the amount of reactivity required in the first place z, r, φ ₁ . For example, a nuclear fission fuel assembly 14 may be part of an igniter assembly for a traveling wave nuclear reactor 12. As another example, a nuclear fission fuel assembly 14 may comprise fissile material obtained from a reproducing isotopic material as a result of the absorption of fast neutrons in the active zone 12 of a traveling wave nuclear reactor and subsequent nuclear conversion into fissile isotopes. As a result, the combustion front 22 of the traveling wave of nuclear fission can propagate too much in the radial direction in the first place z, r, φ ₁ .

As shown in the right figure, the selected nuclear fission subassembly 14 was moved along the lateral measurement φ from the first place z, r, φ ₁ to the second place z, r, φ ₂ . It is clear that the shape of the combustion front 22 of the traveling nuclear fission wave is determined radially as a result of lateral movement of the selected nuclear fission fuel assembly 14 from the first place z, r, φ ₁ to the second place z, r, φ ₂ . The lateral movement of the selected nuclear fission fuel subassembly from the first place z, r, φ ₁ to the second place z, R, φ ₂ removed the fissile content from the first place z, r, φ ₁ and added the fissile content but the second place z, r, φ ₁ . As shown in the right figure, the shape of the combustion front 22 of the traveling wave of nuclear fission shortened along the radial dimension r near the first place z, r, φ ₁ , and lengthened along the radial measurement r near the second place z, r, φ ₂ .

The controlled movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the respective first places to the corresponding second places in block 26 may entail one or more processes. For example, and if we turn to FIGS. 1I and 1J, in some embodiments, the controlled movement of the selected nuclear fission fuel subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places in block 26 may include turning at least one of the selected fuel subassemblies 14 nuclear fission in block 34, as shown by arrow 36 (FIG. IJ). It is clear that the rotation of at least one of the selected nuclear fission subassemblies 14 in block 34 may be performed by any suitable fuel handling system located in the core as required. In addition, it may be necessary to rotate the selected nuclear fission fuel subassemblies 14 in order to minimize or prevent deformation of the reactor construction material, for example, bending of the nuclear fission fuel subassemblies.

As another example, if we turn to FIGS. 1K and 1L, in some other embodiments, the controlled movement of the selected nuclear fission fuel subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places in block 26 may include turning at least one of selected fuel subassemblies 14 of nuclear fission in block 38, as shown by arrows 40 (FIG. IL). It is clear that turning over at least one of the selected nuclear fission fuel assemblies 14 in block 38 may be performed by any suitable fuel handling system located in the core as required. Turning over the nuclear fission subassembly 14 may cause the inlet of the nuclear fission subassembly 14 (before flipping) to become the release of the nuclear fission subassembly 14 (after flipping), and vice versa. This inversion can result in axial equalization of thermal stresses and (or) the effect of radiation on the nuclear fission subassembly 14 on the heaps of the nuclear fission subassembly 14. Any of these radiation actions may be related to temperature and (or) may be associated with changes in the neutron flux at the axial ends of the reactor core 12. It is clear that the inversion of the nuclear fission fuel assembly 14 causes both ends of the inverted nuclear fission fuel assembly 14 to move from first place to second place relative to the central turning point. However, in some cases, it may be necessary to change the assembly location in the lateral direction.

It is also clear that one or more dimensional constraints can be selected as required for a particular application. For example, in some embodiments, the selected set of dimensional constraints may include a predetermined maximum distance along the second dimension.

In some other embodiments, implementation, the selected set of dimensional restrictions may be a function of at least one of the criteria of the combustion front. For example, a criterion for a combustion front may include a neutron flux. In some embodiments, the neutron flux may be associated, but at least with one of the selected nuclear fission fuel assemblies 14. In some other embodiments, the combustion front criterion may include neutron fluence. In some embodiments, the implementation of the neutron fluence may be associated with at least one of the selected nuclear fission fuel subassemblies 14. In some other embodiments, the combustion front criterion may include nuclear fuel burnup. In some embodiments, the burnup of nuclear fuel may be associated with at least one of the selected nuclear fission subassemblies 14. In such embodiments, it may be necessary to move selected nuclear fission subassemblies 14 from a first location having a first burnout rate to a second location having a second burnout rate. Gels selected nuclear fusion subassembly 14 is approaching the top of its service life, then the first place may be a place characterized by a high rate of burnout, and the second place may be a place characterized by a lower burnout rate (relatively high burnout rate in the first place) or almost zero burnout rate. In embodiments in which the nuclear fission fuel assembly 14 is reproduced, it may be necessary to move the nuclear fission fuel assembly 14 from a first location having a low burnup rate to a second location having a higher burnup rate (relative to a burnout of the first place).

In some other embodiments, the implementation of the criteria of the combustion front may include the location of the combustion front within at least one of the selected nuclear fission subassemblies 14. The place of the combustion front can be characterized by signs of the active zone 12 of a traveling wave nuclear reactor or of fuel subassemblies 14 of nuclear fission in it. These features may include, among others, the rate of division, reproduction rate, output power, temperature, reactivity, etc., but not be limited by these parameters.

It is clear that the controlled movement of the selected nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places in block 26 can be performed in any way as required for a particular application. For example, if we turn to FIG. 1M (and as shown in FIGS. 1C and 1D), in some embodiments, the controlled movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the corresponding first places to the corresponding second places in block 26 may include a controlled moving the selected nuclear fission fuel assemblies 14 radially along the first measurement from the corresponding first places to the corresponding second places in block 42. It is clear that the radial movement in block 42 may be performed by any suitable fuel handling system located in the core as required.

In some other embodiments, if we refer further to FIGS. 1N and 10, the controlled movement of the selected nuclear fission fuel subassemblies 14 along the first measurement from the corresponding first places to the corresponding second locations in block 26 may be the controlled movement of the selected nuclear fission fuel subassemblies but spiral along the first measurement from the corresponding first places to the corresponding second places in block 44, as shown by arrow 46. It is clear that the spiral movement in block 44 can be performed by any suitable fuel handling system located in the core as required.

In some other embodiments, if we refer further to FIGS. 1P and 1Q, the controlled movement of the selected nuclear fission subassemblies 14 along the first measurement from the respective first places to the corresponding second locations in block 26 may be a controlled axial movement of the selected nuclear fission subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places in block 48, as shown by arrow 50. It is clear that the axial movement in block 48 can can be performed by any suitable fuel handling system located in the core as required.

It is clear that the shape of the combustion front 22 of the traveling nuclear fission wave can be determined by any parameter associated with the combustion front 22 of the traveling nuclear fission wave, such as an unlimited neutron flux, neutron fluence, burnup and / or reactivity (or any of their components). It is also clear that the combustion front 22 of the traveling wave of nuclear fission can take any form that is required for a particular application. For example, if we turn to FIG. 1R in addition, in some embodiments, the shape of the burning front of the traveling nuclear fission wave can be almost spherical. In some other embodiments, if we refer further to FIG. 1S, the shape of the burning front of the nuclear fission traveling wave 22 can practically correspond to the continuously selected curved surface. In some embodiments, if we refer further to FIG. 1T, the shape of the burning front of the nuclear fission traveling wave can be almost axisymmetric with respect to the second dimension. In some other embodiments, if we turn further to FIGS. 1U and 1V, the shape of the burning front of the nuclear fission traveling wave can have almost n-fold axial symmetry with respect to the second dimension.

It is known to those skilled in the art that maintaining a substantially constant “flat” combustion profile (such as the Bessel function) in the reactor core reduces the formation of sharp maxima among the nuclear fission fuel subassemblies in the core and increases fuel use. In the traveling wave nuclear reactor described above, the combustion region of the reactor typically expands in size due to the high reproduction rate. The combustion area is supported by a sufficient supply of nuclear material, such as reproducing isotopic material or fissile material, to maintain a high reproduction rate.

It is clear that in some reactor designs there are advantages in moving the nuclear fission fuel subassemblies.

as described above in order to maintain the required characteristics of the combustion front. For example, moving the nuclear fission fuel subassemblies radially into the combustion region may act to supply either a reproducing isotopic material or fissile material to the reaction zone. The movement of the nuclear fission fuel subassemblies radially outward can serve to move the nuclear fission fuel subassemblies, having reached their burnup limit, from the zone of high neutron activity. Movement directed radially outward can also serve to reduce the energy density of the combustion region by spreading fissile, fading, nuclear fuel material in areas that have not yet reacted. It is clear that radial movement in combination with spiral movement provides a slower spatial increment of radial movement with azimuthal movement for the further formation of the combustion front. It is also clear that in some cases the fuel subassemblies of nuclear fission can change places (or alternate) with other fuel subassemblies in other places. In these cases, reproducing isotopic material from the reproduction zone can be replaced by well-burnt material from the combustion zone of the reactor. In other cases, the nuclear fuel material may be replaced from places directly adjacent to the reactor core, for example, from two or more replaced places of the nuclear fission fuel subassemblies.

In some embodiments, if we refer further to FIG. 1W, the shape of the burning front of the nuclear fission traveling wave along the second dimension may be asymmetric. In some embodiments, the shape of the burning front of the nuclear fission traveling wave may be axisymmetric (characterized by axial asymmetry) with respect to the second dimension.

In some embodiments, if we refer additionally to FIG. IX, method 20 may also include a stage in which (at block 52) a combustion front of a traveling nuclear fission wave is ignited by igniter assemblies (not shown) of a nuclear fission traveling wave (not shown). Illustrative examples of the initiation of a traveling wave of nuclear fission by assemblies of the igniter of a traveling wave of nuclear fission are described above, and there is no need for repetition. Turning further to FIG. 1Y. At a block 54, at least one of the nuclear fission traveling wave igniter assemblies may be removed before the controlled movement of selected nuclear fission fuel subassemblies along the first measurement from respective first places to corresponding second places. Turning further to FIG. 1Z. In some embodiments, the removal of at least one of the nuclear fission traveling wave igniter assemblies in block 54 before the controlled movement of the selected nuclear fission fuel subassemblies along the first measurement from the respective first places to the corresponding second places may include (in block 56) at least one of the assemblies of the nuclear fission traveling wave igniter from second places before the controlled movement of the selected nuclear fission fuel subassemblies along the first measurement I am from the corresponding first places to the corresponding second places.

In some embodiments, if we turn to FIG. IAA, in block 58 it is caused that the traveling wave nuclear reactor becomes subcritical before the controlled movement of the selected nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places. For example, if we turn to FIG. 1AB, in some embodiments, causing the traveling wave nuclear reactor to become subcritical (at block 58) may include introducing neutron-absorbing material into the reactor core in block 60.

Turning further to FIG. 1AC. In some embodiments, at block 62, criticality can be restored after a controlled movement of selected nuclear fission fuel subassemblies along a first measurement from respective first places to corresponding second places. For example, if we turn to FIG. 1AD, in some embodiments, the restoration of criticality in block 62 may include removing at least a portion of the neutron-absorbing material from the reactor core in block 64.

In some embodiments, if we refer further to FIG. 1AE, in block 66 a traveling wave nuclear reactor can be stopped before the controlled movement of selected nuclear fission fuel subassemblies along the first measurement from corresponding first places to corresponding second places. Turning further to FIG. 1AF. At a block 68, a traveling wave nuclear reactor can be restarted after a controlled movement of selected nuclear fission fuel subassemblies along a first measurement from respective first places to corresponding second places.

Turning now to FIG. 2A to FIG. 1B. An illustrative method 200 is provided for controlling a traveling wave nuclear reactor in which the combustion front of a traveling nuclear fission wave propagates along the first and second dimensions. The method 200 starts at block 202. At block 204, the desired shape of the burning front of the nuclear fission traveling wave 22 along the second dimension in the nuclear fission fuel subassemblies 14 is determined in accordance with the selected set of dimensional constraints. In block 206, the movement of the selected nuclear fission subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places is determined, depending on the desired shape.

Turning further to FIG. 2B, in some embodiments, an existing shape of a burning front of a nuclear fission traveling wave is determined in block 210. It is clear that the determination of the existing shape of the nuclear fission traveling wavefront 22 in block 210 may be performed as required to determine the desired shape of the nuclear fission traveling wavefront 22 in block 204. In some embodiments, the determination of the existing shape of the traveling wavefront of firing 22 nuclear fission in block 210 can be performed before determining the desired shape of the front of burning 22 of the traveling wave of nuclear fission in block 204. In some other embodiments, the implementation of the definition of the existing form f the nuclear fission of the running nuclear fission wave in the block 210 can be performed almost simultaneously with the determination of the desired shape of the nuclear fission of the traveling nuclear fission wave 22 in the block 204. In some other embodiments, the determination of the existing shape of the nuclear fission of the traveling nuclear fission wave 22 in block 210 can be performed after determining the desired shape of the burning front of the nuclear fission traveling wave in block 201. The desired shape can be determined as required, including determining the fission rate, the estimated burnup, reproduction rate, temperature distribution, distribution of energy density, history of assembly operation and reactivity of displaced nuclear fuel in appropriate places.

It is clear that the selected nuclear fission fuel assemblies 14 can be moved for any purpose, as is required for a particular application, for example, to establish the desired shape of the nuclear fission wave traveling combustion front 22 and / or to maintain the desired shape of the nuclear fission traveling wave combustion front 22 . For example, in some embodiments, if we refer additionally to FIG. 2C, determining the movement of the selected nuclear fission subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape in block 206 may include determining the movement of the selected fuel subassemblies 14 nuclear fission along the first measurement from the corresponding first places to the corresponding second places so as to establish the desired shape, in block 212. In some cases In other embodiments, if we turn further to FIG. 2D, determining the movement of the selected nuclear fission subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape may include determining the movement of the selected nuclear fission fuel subassemblies 14 along the first measurement from the corresponding first places in the corresponding second places so as to maintain the desired shape in block 214.

It is clear that it may be necessary to determine, among other things, the time when to perform the required movement. For this purpose, and if we turn to FIG. 2E, in some embodiments, block 216 determines the time when to move the selected nuclear fission fuel subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape. It is also clear that the determination in block 216 can be performed at any time during the implementation of method 200, as required.

In some embodiments, selected nuclear fission subassemblies 14 may be moved. Turning further to FIG. 2F. At a block 218, selected nuclear fission subassemblies 14 may move along a first dimension from respective first places to corresponding second places depending on the desired shape.

It is clear that some aspects of the method 200 are similar to some of the aspects of the method 10, which are explained above. These similar aspects will be mentioned, but for brevity there is no need to re-explain their details for understanding.

For example, if we turn further to FIG. 1B, in some embodiments, the nuclear fission fuel assemblies 14 may be elongated along the second dimension. The first measurement may be substantially orthogonal to the elongated axis of the nuclear fission subassemblies 14. The first dimension and the second dimension can be practically orthogonal to each other.

In further examples and still referring to FIG. 1B, the first dimension may be a radial dimension, and the second dimension may be an axial dimension. In some other examples, the first dimension may be an axial dimension, and the second dimension may be a radial dimension. Nuclear fission reactors of any type may contain nuclear fission fuel subassemblies that extend over the entire axial dimension, with several nuclear fission fuel subassemblies that undergo a radial measurement. A traveling nuclear fission wave can propagate along and along the axial measurement at a different speed than in the radial measurement, depending on the distribution of energy release density and divergence (deviations), in this case, a traveling nuclear fission wave from internal zones to external zones, especially in structural versions with a cylindrical reactor core. In this case, it is required to perform radial movements of the nuclear fission fuel subassemblies in order to preserve the waveform and characteristics in the axial dimension. For example, the propagation of a traveling nuclear fission wave within the axis of the reactor zone will contribute to neutron leakage from the reactor core at the axial ends of the reactor core. This leak, as described above, reduces the conversion of reproducing nuclei to fissile in a nuclear fission reactor. The nuclear fission fuel subassemblies with a combustion front that propagates to undesirable axial locations can be radially moved so that the nuclear fission fuel subassemblies undergo neutron activity in places in the nuclear fission fuel subassembly that reduce and (or) limit the further propagation of the combustion front to undesirable places. In other cases, it may be necessary to move the nuclear fission fuel subassemblies radially based on the propagation of the nuclear fission traveling wave in the axial dimension so that fissile material reproduced in the axial regions of the nuclear fission fuel subassembly can be used in other parts of the core of the nuclear fission reactor. At this axial location, the combustion front can be made uneven in the radial measurement by controlled movement of the fuel subassemblies of nuclear fission so that, if necessary, alternative zones of changing enrichment could be created in this. The location of the high enrichment zones near the spent or depleted fuel zones increases the neutron leakage from the high enrichment zones to low enrichment zones, thereby contributing to the conversion of the reproducing isotopic material into fissile material. It is clear that the aforementioned movements can be made to facilitate propagation in the first dimension, while limiting propagation in the second dimension.

In some other examples, if we continue to refer in addition to FIG. 1B, the first dimension may be an axial dimension, and the second dimension may be a lateral dimension. In other examples, the first dimension may be a lateral dimension, and the second dimension may be an axial dimension.

As already noted, and if we turn further to FIG. 1C, the first places may be outwardly directed places 30 and the second places may be inwardly directed places 32. And as already noted, the inwardly directed places 32 and outwardly directed places 30 may be based on geometric proximity to the central part of the reactor core 12. Inwardly directed locations 32 and outwardly directed locations 30 may be based on a neutron flux such that the neutron flux in inwardly directed locations 32 is greater than the neutron flux in outwardly directed locations 30. As already noted, inwardly directed locations 32 and outwardly directed locations 30 can be based on reactivity so that k _effective in inwardly directed places 32 is higher than k _effective in outwardly directed places 30.

In some embodiments, implementation, if we refer in addition to fig.1D. the first places can be inwardly directed places 32 and the second places can be outwardly directed places 30. The inwardly directed places and outwardly directed places can be based on the geometric proximity to the central part of the reactor core 12, and (or) based on the neutron flux so in that the neutron flux field directed inward more than the neutron flux in the outward locations, and (or) based on reactivity so that k _effective in inwardly directed field higher than in n k _effective out-directional field.

In some embodiments, and as shown in FIG. 1B, first places and second places may be located on opposite sides of the reference value along the first measurement.

As also shown in FIG. in some embodiments, the first places and second places may include at least one attribute that is substantially equal. For example, at least one attribute may include a geometric proximity to the central region of the reactor core 12, a neutron flux, and / or reactivity.

In some embodiments, if we refer further to FIG. 2G, determining the movement of the selected nuclear fission fuel subassemblies 14 along the first measurement from the respective first places to the corresponding second locations in block 206 may include determining the rotation of at least one of the selected nuclear fission fuel subassemblies 14 in block 220. In some embodiments, if we refer further to FIG. 211. determining the movement of the selected nuclear fission fuel subassemblies 14 along the first measurement from the respective first places to the corresponding second places in block 206 may include determining that at least one of the selected nuclear fission fuel subassemblies 14 is turned over in block 222.

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 is a function of at least one of the criteria of the combustion front. For example, a combustion front criterion may include a neutron flux, such as an unlimited neutron flux associated with at least one of the selected fuel subassemblies 14. As yet another example, a combustion front criterion may include a neutron fluence, such as without limiting fluence neutrons associated with at least one of the selected nuclear fission subassemblies 14. As another example, a combustion front criterion may include burnout, such as unlimited burnout, associated with at least one of the selected nuclear fission fuel assemblies 14. In some other embodiments, the implementation of the criterion of the combustion front may include the location of the combustion front in at least one of the selected nuclear fission subassemblies 14.

Turning further to FIG. In some embodiments, the determination of the movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the respective first places to the corresponding second places in the block 206 may include determining the radial movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the corresponding first places to the corresponding second places in the block 224. In some embodiments, if we refer further to FIG. 25, determining the movement of the selected heat dissipation nuclear fission subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places in block 206 may include determining the spiral movement of the selected nuclear fission subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places in block 226. In some other embodiments if we turn in addition to fig.2K. determining the movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the respective first places to the corresponding second places in block 206 may include determining the axial movement of the selected nuclear fission fuel assemblies 14 in block 228.

Turning further to FIG. 2L. In some embodiments, determining a desired shape of a nuclear fission traveling wavefront 22 in block 204 may include determining a substantially spherical shape of a nuclear fission traveling wavefront 22 in block 230. In some other embodiments, if we refer further to FIG. 2M, determining the desired the shape of the burning front of the nuclear fission traveling wave along the second dimension in block 204 may include determining the shape of the continuously curved surface of the burning front of the nuclear flying wave 22 th division in block 232. In some other embodiments, the curved surface may be performed such as to increase the surface area of the combustion front. In these embodiments, neutron leakage from the combustion zones to the reproduction zones is enhanced.

The desired shape of the combustion front 22 of the traveling wave of nuclear fission can be any. As already noted, in various embodiments, the desired shape of the combustion front 22 of the traveling wave of nuclear fission can be practically axisymmetric with respect to the second dimension; the required shape of the burning front of the nuclear fission traveling wave may have practically n-fold axial symmetry with respect to the second dimension; the desired shape of the burning front of the traveling wave of nuclear fission may be asymmetric; and (or) the desired shape of the combustion front 22 of the traveling wave of nuclear fission may be axisymmetric with respect to the second dimension. In some other embodiments, symmetrical n-fold symmetry forms can be converted to separate combustion zones in a traveling wave nuclear reactor. For example, a combustion front can transform into petals that propagate into n or fewer separate (i.e., neutron-isolated) combustion zones (see FIG. 1V).

Some embodiments may be presented as illustrative systems. For example, as shown in FIG. 3A, an exemplary system 300 is provided for determining the movement of nuclear fission fuel subassemblies (not shown in FIG. 3A). As one non-limiting example, system 300 can provide a suitable system environment for implementing method 200 (FIGS. 2A-2M). In some embodiments, if we refer additionally to FIG. 1B, for a nuclear fission traveling wavefront 22 propagating in the first and second dimensions, circuitry 302 is provided to determine the desired shape of the nuclear fission traveling wavefront 22 along the second dimension in the fuel subassemblies 14 nuclear fission in accordance with the selected set of size limits. Electrical circuits 304 are provided to determine the movement of the selected nuclear fission fuel subassemblies 14 along the first measurement from the respective first locations to their respective second locations depending on the desired shape.

In a general sense, specialists will understand that the various aspects described in this document, which can be implemented - separately and (or) together - by a variety of hardware, types of software, software and hardware and / or any combination thereof, can be considered as consisting of various types of "electrical circuits". Therefore, in the sense in which it is used in the present description, the term "electrical circuits" includes, without limitation, electrical circuits having at least one discrete electrical circuit; electrical circuits having at least one integrated circuit; electrical circuits having at least one specialized integrated circuit; electrical circuits forming a universal computing device configured by a computer program (eg, a universal computer configured by a computer program that at least partially implements the processes and / or devices described herein or a microprocessor configured by a computer program which, at least partially implements the processes; and (or) the devices described herein); electrical circuits forming a storage device (for example, types of memory (for example, random access memory, flash memory, read-only memory, etc.)); and (or) electrical circuits forming a communication device (for example, a modem, communication switch (switch), optoelectric equipment, etc.). Those skilled in the art will understand that the subject matter described herein may be implemented in analog or digital form or in some combination thereof.

Turning further to FIG. 3B. In one illustrative example, electrical circuits 302 and / or electrical circuits 304 may be implemented as a computing system 306 (which may also be referred to as a host computer or host system). In the illustrated embodiment, a central processing unit (“CPU”) (or microprocessor) 308 is connected to the system bus 310. A random access memory (“RAM”) 312 is connected to the system bus 310 and provides the CPU 308 with access to the storage device 314 (which can be used to storing data associated with one or more parameters of the combustion front 22 of a traveling wave of nuclear fission). When executing programmed instructions, the CPU 308 stores these process steps in the RAM 312 and executes the stored process steps from the RAM 312.

Computing system 306 may be connected to a computer network (not shown) using a network interface 316 and through a network connection (not shown). One such network is the Internet, which allows computing system 306 to download an application, code, documents, and other electronic information.

Read Only Memory (“RUM”) 318 is provided for storing invariant command sequences, such as start command sequences or basic operating system I / O (BIOS) sequences.

The input / output device interface (“I / O”) 320 allows the computing system 306 to connect to various input / output devices, for example, a keyboard, pointing device (“mouse”), monitor, printer, modem, and the like. The I / O device interface 320 is shown as a single unit for simplicity, but may be several interfaces for interfacing with various types of I / O devices.

It is clear that the embodiments are not limited to the architecture of the computing system 306 shown in FIG. 3B. Depending on the type of business application / environment, the computing system 306 may have more or fewer components. For example, computing system 306 may be a set top box, laptop, laptop, desktop system, or other types of systems.

In various embodiments, portions of the disclosed systems and methods include one or more computer program products. A computer program product includes a computer-readable storage medium, such as a non-volatile storage medium, and portions of a computer-readable control program, such as a set of computer programs embodied in a computer-readable storage medium. Typically, a computer program is stored and executed by a processor or associated storage device, such as the processing components shown in FIG. 3B.

In this regard, FIGS. 2A-2M and 3A-3C are flowcharts of methods, systems, and software products, respectively, in accordance with various embodiments. It is understood that each block of flowcharts and combinations of blocks in flowcharts can be implemented by computer program instructions. These commands of computer programs can be loaded into a computer or other programmable device to create a mechanism so that the commands that are executed on a computer or other programmable device create means for implementing the functions indicated in the block diagram (block diagrams). These commands of computer programs can also be loaded into computer-readable memory, which can command a computer or other programmable device to act in a specific way so that instructions stored in computer-readable memory create a product, including command tools that implement the function indicated on the block diagram (flowcharts). These computer program instructions can also be downloaded to a computer or other programmable device to ensure that a number of operational steps are performed on a computer or other programmable device, to create a computer-implemented process so that instructions that are executed by a computer or other programmable device create stages for implementing functions indicated on the flowchart (flowcharts).

Accordingly, the blocks of the flowchart support combinations of means for performing the specified functions, combinations of stages for performing the specified functions and software command means for performing the specified functions. It is also clear that each block of the block diagram and combinations of blocks in the block diagram (block diagrams) can be implemented by special computer systems based on hardware that perform the specified functions or stages, or by combinations of special hardware and machine instructions.

Turning further to FIG. 3C. In some embodiments, electrical circuits 304 may also be used to determine the existing shape of the burning front of a nuclear fission traveling wave. For example, sensors 322 may be operatively connected to electrical circuits 304 in a signal message via an appropriate input interface 324. Sensors 322 may include any suitable sensor that measures a specific parameter of a combustion front 22 of a traveling nuclear fission wave. For example, sensors 322 can measure neutron flux, neutron fluence, fading, and / or reactivity (or any component thereof).

As already noted, embodiments of the system 300 and circuitry 302 and 304 may be designed to create a suitable system environment for implementing method 200 (FIGS. 2A-2M) (regardless of whether computer program instructions are loaded into a computer or other programmable device to create mechanism), so that the commands that are executed on a computer or other programmable device create means for implementing the functions indicated on the block diagram (block diagrams), or each block of the block diagram and combination of blocks on the block -scheme (flowcharts) implemented by special computer systems based on the hardware that perform the specified functions or steps, or combinations of special hardware and computer instructions. Some features of embodiments of the system 300 will be discussed with reference further to FIGS. 1B-D, 1J, 1L, 1O, 1Q, 1R-1W and 2A-2M.

To this end, in some embodiments, the electrical circuits 304 may also be used to determine the movement of the selected nuclear fission fuel subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places so as to establish the desired shape. The electrical circuits 304 may also be used to determine the movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the corresponding first places to the corresponding second places so as to maintain the desired shape. Electrical circuits 304 can also be used to determine the time by moving the selected nuclear fission subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

As already noted, in some embodiments, the nuclear fission fuel assemblies 14 may be elongated along the second dimension.

As already noted, in some embodiments, the first measurement may be substantially orthogonal to the elongated axis of the nuclear fission subassemblies 14. In some other embodiments, the first dimension and the second dimension may be substantially orthogonal to each other.

In various embodiments, the first dimension may be a radial dimension, and the second dimension may be an axial dimension; the first dimension may be an axial dimension, and the second dimension may be a radial dimension; the first dimension may be an axial dimension, and the second dimension may be a lateral dimension; and / or the first dimension may be a lateral dimension, and the second dimension may be an axial dimension.

In some embodiments, the first places may be outwardly directed places 30, and the second places may be inwardly directed places 32. Inwardly directed places 32 and outwardly directed places 30 may be based on various attributes as required, such as, without limitation, geometric proximity to the neutral part of the reactor core 12, a neutron flux (so that the neutron flux in inwardly directed places 32 is greater than the neutron flux in outwardly directed places 30), and (or ) Reactivity (so that the k _effective in field 32 directed inward is higher than the k _effective in field 30 outward.

In some other embodiments, the first seats may be inwardly directed seats 32, and the second seats may be outwardly directed seats 30. Inwardly directed seats 32 and outwardly directed seats 30 may be based on various attributes as desired, such as without limitation. geometrical proximity to the central part of the reactor core 12, neutron flux (so that the neutron flux in inwardly directed places 32 is greater than the neutron flux in outwardly directed places 3 0), and (or) reactivity (so that k _effective in inwardly directed places 32 is higher than k _effective in outwardly directed places 30). In some embodiments, the first places and second places may be on opposite sides of the initial value along the first dimension.

In some other embodiments, the first places and second places may include at least one attribute that is substantially equal. For example, at least one attribute may be a geometric proximity to the central region of the reactor core 12, a neutron flux, and / or reactivity.

In some embodiments, electrical circuits 304 may also be used to determine the rotation of at least one of the selected nuclear fission subassemblies 14. In some other embodiments, electrical circuits 304 may also be used to determine the inversion of at least one of the selected nuclear fission fuel assemblies 14.

As already noted, in some embodiments, the selected set of dimensional constraints may include a predetermined maximum distance along the second dimension.

In some other embodiments, the implementation of the selected set of dimensional restrictions may be a function of at least one criterion of the combustion front. For example, a combustion front criterion may include, without limitation: a neutron flux, such as a neutron flux associated with at least one of a selected nuclear fission fuel assembly 14; a neutron fluence, such as a neutron fluence, associated with at least one of a selected nuclear fission fuel subassembly 14; and / or burnout, such as burnout, associated with at least one of the selected nuclear fission subassemblies 14. In some embodiments, the burning front criterion may include the location of the burning front in at least one of the selected nuclear fission fuel assemblies 14.

In some embodiments, electrical circuits 304 may also be used to determine the radial movement of selected nuclear fission fuel subassemblies 14 along a first measurement from respective first places to corresponding second places. The electrical circuits 304 may also be used to determine the spiral movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the corresponding first places to the corresponding second places. Electrical circuits 304 can also be used to determine the axial displacement of selected nuclear fission subassemblies 14

In some embodiments, electrical circuits 302 can also be used to determine the almost spherical shape of the combustion front 22 of a traveling nuclear fission wave. Electrical circuits 302 can also be used to determine the shape of a continuously curved surface of the combustion front 22 of a traveling nuclear fission wave.

In various embodiments, the desired shape of the combustion front of the traveling nuclear fission traveling wave 22 may be substantially axisymmetric with respect to the second dimension; can have almost n-fold axial symmetry relative to the second dimension; and (or) may be asymmetric, for example, without limiting axisymmetric relative to the second dimension.

As another example, if we turn now to FIG. 4A, another illustrative system 400 is proposed for moving nuclear fission fuel subassemblies (not shown in FIG. 4A). As one non-limiting example, system 400 can provide a suitable system environment for implementing method 100 (FIGS. 1A-1AF). Accordingly, the following description is given with further reference to FIGS. 1A-1AF.

In some embodiments, for a burning front of a nuclear fission traveling wave propagating in the first and second dimensions, electrical circuits 402 are used to determine the desired shape of a burning nuclear fission wave front 22 along a second dimension in the nuclear fission fuel subassemblies 14 according to the selected set dimensional restrictions. The electrical circuits 404 are intended to determine the movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape. The subassembly 405 is designed to move selected nuclear fission subassemblies 14 responsive to the electrical circuits 404.

It is clear that the electrical circuits 402 and 404 may be similar to the electrical circuits 302 and 304. In some cases, the electrical circuits 402 and 404 may be the same as the electrical circuits 302 and 304. Therefore, for brevity, it is not necessary to repeat the details for understanding. .

As a brief overview, if we turn to FIG. 4B, in an illustrative example, the electrical circuits 402 and / or the electrical circuits 404 may be implemented as a computing system 406 (which may also be referred to as a host computer or host system). In the illustrated embodiment, a central processing unit (“CPU”) (or microprocessor) 408 is connected to the system bus 410. Random Access Memory (“RAM”) 412 is connected to the system bus 410 and provides the CPU 408 with access to the storage device 414 (which can be used to storing data associated with one or more parameters of the combustion front 22 of a traveling wave of nuclear fission). When executing programmed instructions, the CPU 408 stores these process steps in RAM 412 and executes the stored process steps from RAM 412. Computing system 406 can be connected to a computer network (not shown) using a network interface 416 and via a network connection (not shown). Read only memory (“ROM”) 418 is provided for storing invariant command sequences, such as start command sequences or basic operating system input / output (BIOS) sequences. The interface of the input-output devices ("I / O") 420 allows the computing system 406 to connect to various input-output devices, for example, a keyboard, pointing device ("mouse"), monitor, printer, modem, etc. It is clear that the embodiments are not limited to the architecture of the computing system 406 shown in FIG. The description of the non-limitation regarding the computing system 306 (FIG. 3B) extends to the computing system 406.

In various embodiments, portions of the disclosed systems and methods include one or more computer program products. The above description regarding computer software products associated with system 300 (FIG. 3A) applies to system 400 as well.

In this regard, FIGS. 1A, 1I, 1K, 1M-1N, 1P, and 1X-1AF and 4A-4C are flowcharts of methods, systems, and software products in accordance with various embodiments. It is understood that each block of flowcharts and combinations of blocks in flowcharts can be implemented by computer program instructions. These commands of computer programs can be loaded into a computer or other programmable device to create a mechanism so that the commands that are executed on a computer or other programmable device create means for implementing the functions indicated in the block diagram (block diagrams). These commands of computer programs can also be loaded into computer-readable memory, which can command a computer or other programmable device to act in a specific way so that instructions stored in computer-readable memory create a product, including command tools that implement the function indicated on the block diagram (flowcharts). These commands of computer programs can also be loaded into a computer or other programmable device to ensure that a number of operational stages are performed in a computer or other programmable device, to create a computer-implemented process, so that the commands that are executed by a computer or other programmable device create stages for implementing functions, indicated on the flowchart (flowcharts).

Accordingly, the blocks of the flowchart support combinations of means for performing the specified functions, combinations of stages for performing the specified functions and software command means for performing the specified functions. It is also clear that each block of the block diagram and combinations of blocks in the block diagram (block diagrams) can be implemented by special computer systems based on hardware that perform the specified functions or stages, or by combinations of special hardware and machine instructions.

Turning further to FIG. 4C. In some embodiments, electrical circuits 404 can also be used to determine the existing shape of the burning front of a nuclear fission traveling wave. For example, the sensors 422 can be functionally connected to the electrical circuits 404 in a signal message via the corresponding input interface 424. The electrical circuits 404, the sensors 422 and the input interface 424 can be similar (and in some cases identical) to the electric circuits 304, sensors 322 and the input interface 324 (all in FIG. 3C). To understand the repetition of their details is not required.

As already noted, embodiments of the system 400, electrical circuits 402 and 404, and subassemblies 405 may be designed to create a suitable system environment for implementing method 100 (FIGS. 1A, 1I, 1K, 1M-1N, 1P, and 1X-1AF), independently whether computer program instructions are loaded into a computer or other programmable device to create a mechanism, so that the commands that are executed on a computer or other programmable device create means for implementing the functions indicated on the block diagram (block diagrams), or each block flowcharts S and combinations of blocks on a block diagram (block diagrams) were implemented by special computer systems based on hardware that perform the specified functions or stages, or by combinations of special hardware and machine instructions. Some features of embodiments of the system 400 will be discussed with reference further to FIGS. 1A-1AF.

In some embodiments, as shown in FIG. 4C, electrical circuits 404 may also be used to determine the existing shape of the combustion front 22 of a traveling nuclear fission wave. This determination can be made in a similar or identical manner as in the case of electrical circuits 304 (FIG. 3A). as described above. To this end, the sensors 422 and the input interface 424 are similar or (in some cases) identical to the sensors 322 and the input interface 324 in FIG. 3C. Sensors 422, input interface 424, and electrical circuits 404 interact, as already noted for sensors 322, input interface 324, and electrical circuits 304 (all in FIG. 3C).

In some embodiments, the electrical circuits 404 may also be used to determine the movement of the selected nuclear fission fuel subassemblies 14 along the first measurement from the respective first locations to their respective second locations so as to establish the desired shape. In some other embodiments, electrical circuits 404 may also be used to determine the movement of the selected nuclear fission fuel subassemblies 14 along the first measurement from the respective first locations to their respective second locations so as to maintain the desired shape.

In some embodiments, electrical circuits 404 may also be used to determine when to move selected nuclear fission subassemblies 14 along a first measurement from respective first places to corresponding second places depending on the desired shape.

In some embodiments, nuclear fission subassemblies 14 may be elongated along a second dimension. The first measurement may be substantially orthogonal to the elongated axis of the nuclear fission subassemblies 14. The first dimension and the second dimension can be practically orthogonal to each other.

In various embodiments, the first dimension may be a radial dimension, and the second dimension may be an axial dimension; the first dimension may be an axial dimension, and the second dimension may be a radial dimension; the first dimension may be an axial dimension, and the second dimension may be a lateral dimension; and / or the first dimension may be a lateral dimension, and the second dimension may be an axial dimension.

In some embodiments, the first locations may be outwardly directed locations 30, and the second locations may be inwardly oriented locations 32. Inwardly directed locations 32 and outwardly oriented locations 30 may be based on: geometric proximity to the central portion of the reactor core 12; the neutron flux so that the neutron flux in the inwardly directed places 32 is greater than the neutron flux in the outwardly directed places 30, and (or) the reactivity so that k _effective in the inwardly directed places 32 is higher than k _effective in the outwardly directed places 30.

In some other embodiments, the first locations may be inwardly directed locations 32, and the second locations are outwardly oriented locations 30. Inwardly directed locations and outwardly oriented locations may be based on the geometric proximity to the central portion of the reactor core 12; the neutron flux so that the neutron flux in the inwardly directed places 32 is greater than the neutron flux in the outwardly directed places 30, and (or) the reactivity so that k _effective in the inwardly directed places 32 is higher than k _effective in the outwardly directed places 30.

In some embodiments, the first places and second places may be on opposite sides of the initial value along the first dimension.

In some other embodiments, the first places and second places may include at least one attribute that is substantially equal. For example, at least one attribute may include a geometric proximity to the central region of the reactor core 12; neutron flux; and / or reactivity.

In various embodiments, electrical circuits 404 can also be used to determine the rotation of at least one of the selected nuclear fission fuel assemblies 14. Electrical circuits 404 can also be used to determine the reversal of at least one of the selected nuclear fission subassemblies 14.

The sub-assembly 405 may include any known suitable nuclear fuel handling device, such as, but not limited to, a nuclear fuel handling device located in the core. However, in some other embodiments, subassembly 405 may include a nuclear fuel handling device located outside the core.

Regardless of the shape in which subassembly 405 is made, in various embodiments, subassembly 405 can also be used to radially move selected nuclear fission fuel assemblies 14 from corresponding first places to corresponding second places. The subassembly 405 may also be used for the helical movement of the selected nuclear fission fuel assemblies 14 from the corresponding first places to the corresponding second places. The subassembly 405 may also be intended for axial movement of the selected nuclear fission fuel subassemblies.

In some embodiments, subassembly 405 may also be designed to rotate selected nuclear fission subassemblies 14. In some other embodiments, subassembly 405 can also be used to flip selected nuclear fission subassemblies 14. Turning now to Fig. 5. In various embodiments, an illustrative traveling wave 500 nuclear reactor may be provided. A traveling wave 500 nuclear reactor includes an active region 12 of a traveling wave nuclear reactor. As already noted, the fuel subassemblies 14 of nuclear fission are received in the active zone 12 of a traveling wave nuclear reactor. Each of the nuclear fission fuel subassemblies 14 is designed to propagate in it a combustion front 22 of a traveling nuclear fission wave along the first and second dimensions. Electrical circuits 402 are designed to determine the desired shape of the combustion front 22 of a traveling nuclear fission wave along the second dimension in the nuclear fission fuel subassemblies 14 in accordance with the selected set of dimensional constraints. Electrical circuits 404 are designed to determine the movement of selected nuclear fission fuel subassemblies 14 along a first measurement from respective first places to corresponding second places depending on the desired shape. The subassembly 405 is designed to move selected nuclear fission subassemblies 14 responsive to the electrical circuits 404.

Thus, the reactor 500 can be configured as the reactor core 12 described above in combination with and interacting with the system 400. also described above. Since the details regarding the core 12 of the reactor (and its components) and the system 400 (and its components) are set forth above, it is not necessary to repeat them for understanding.

As already noted, in various embodiments, electrical circuits 404 can also be used to determine the existing shape of the combustion front 22 of a traveling nuclear fission wave. The electrical circuits 404 can also be used to determine the movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the corresponding first places to the corresponding second places so as to establish the desired shape. The electrical circuits 404 may also be used to determine the movement of the selected nuclear fission subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places so as to maintain the desired shape.

As already noted, in some embodiments, electrical circuits 404 can also be used to determine when to move selected nuclear fission fuel assemblies 14 along a first measurement from their respective first locations to their respective second locations depending on the desired shape.

In some embodiments, the nuclear fission fuel assemblies 14 may be elongated along a second dimension.

In some embodiments, the first measurement may be substantially orthogonal to the elongated axis of the nuclear fission subassemblies 14. In some embodiments, the first measurement and the second measurement may be substantially orthogonal to each other.

In various embodiments, the first dimension may be a radial dimension, and the second dimension may be an axial dimension; the first dimension may be an axial dimension, and the second dimension may be a radial dimension; the first dimension may be an axial dimension, and the second dimension may be a lateral dimension; and / or the first dimension may be a lateral dimension, and the second dimension may be an axial dimension.

In some embodiments, the first locations may be outwardly directed locations 30, and the second locations are inwardly oriented locations 32. Inwardly directed locations 32 and outwardly oriented locations 30 may be based on the geometric proximity to the central portion of the reactor core 12; the neutron flux so that the neutron flux in the inwardly directed places 32 is greater than the neutron flux in the outwardly directed places 30; and (or) reactivity so that k _effective in inwardly directed locations 32 is higher than k _effective in outwardly oriented locations 30.

In some other embodiments, the first locations may be inwardly directed locations 32, and the second locations may be outwardly oriented locations 30. Inwardly directed locations 32 and outwardly oriented locations 30 may be based on the geometric proximity to the central portion of the reactor core 12; the neutron flux so that the neutron flux in the inwardly directed places 32 is greater than the neutron flux in the outwardly directed places 30; and (or) reactivity so that k _effective in inwardly directed places 32 is greater than k _effective in outwardly directed places 30.

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

In some embodiments, the first places and second places may include at least one attribute that is substantially equal. At least one attribute may include a geometric proximity to the central region of the reactor core 12, a neutron flux, and / or reactivity.

In various embodiments, and as already noted, electrical circuits 404 can be used to determine the rotation of at least one of the selected nuclear fission subassemblies 14 and / or to be used to determine the reversal of at least one of the selected nuclear fuel subassemblies 14 nuclear fission.

In some embodiments, the selected set of dimensional constraints may include a predetermined maximum distance along the second dimension. In some other embodiments, the implementation of the selected set of dimensional restrictions may be a function of at least one criterion of the combustion front, such as without limitation: a neutron flux, such as a neutron flux associated with at least one of the selected fuel subassemblies 14 nuclear fission; a neutron fluence, such as a neutron fluence, associated with at least one of a selected nuclear fission fuel subassembly 14; and / or burnout, such as burnout, associated with at least one of the selected nuclear fission subassemblies 14. In some other embodiments, the implementation of the criterion of the combustion front may include the location of the combustion front in at least one of the selected nuclear fission subassemblies 14.

In various embodiments, electrical circuits 404 can also be used to determine the radial movement of selected nuclear fission fuel subassemblies 14 along a first measurement from respective first places to corresponding second places. Electrical circuits 404 can also be used to determine the spiral movement of selected nuclear fission fuel subassemblies 14 along a first measurement from respective first places to corresponding second places.

Electrical circuits 404 may also be used to determine the axial displacement of selected nuclear fission subassemblies 14.

In various embodiments, electrical circuits 402 can also be used to determine the practically spherical shape of the nuclear fission traveling wave front 22 and / or the continuously curved surface shape of the nuclear fission traveling wave front 22. The desired shape of the combustion front 22 of the traveling wave of nuclear fission can be practically axisymmetric with respect to the second dimension; can have almost n-fold axial symmetry relative to the second dimension; and / or may be asymmetric, such as axisymmetric with respect to the second dimension.

In some embodiments, subassembly 405 may include a nuclear fuel handling device. As already noted, subassembly 405 may include any known suitable nuclear fuel handling device, such as, but not limited to, a nuclear fuel handling device located in the core. However, in some other embodiments, subassembly 405 may include a nuclear fuel handling device located outside the core.

In addition, as already noted, in various embodiments, subassembly 405 can also be used to radially move selected nuclear fission subassemblies 14 from respective first places to corresponding second places. The subassembly 405 may also be used for the helical movement of the selected nuclear fission fuel assemblies 14 from the corresponding first places to the corresponding second places. The subassembly 405 may also be intended for axial movement of the selected nuclear fission subassemblies 14. The subassembly 405 can also be used to rotate the selected nuclear fission subassemblies 14. The subassembly 405 can also be used to invert selected nuclear fission subassemblies 14.

Turning now to FIG. In some embodiments, a method 600 is provided for controlling a traveling wave nuclear reactor. Method 600 begins at block 602. Turning further to FIG. 1B. At a block 604, at least one nuclear fission fuel assembly 14 is moved outward from a first place in a traveling wave nuclear reactor 12 to a second place in a traveling wave nuclear reactor 12. Method 600 is stopped at block 606.

In some embodiments, if we refer further to FIG. 6B, at block 608, at least one nuclear fission fuel assembly 14 can be moved inward from a second location.

In various embodiments, the first places and second places can be based on the geometric proximity to the neutral part of the reactor core 12, the neutron flux so that the neutron flux in the first places is greater than the notes of the neutrons in the second places, and reactivity so that k is _effective in first places more than k _effective in second place.

We turn now to Fig.7. In some embodiments, a method 700 is provided for controlling a traveling wave nuclear reactor. Method 700 begins at block 702. Turning further to FIG. 1B. At a block 704, a movement of at least one nuclear fission assembly 14 in a first direction from a first place in a traveling wave nuclear reactor 12 to a second place in a traveling wave nuclear reactor 12 is determined. Second place is different from first place. At a block 706, a movement of at least one nuclear fission assembly 14 in a second direction from a second position is determined. The second direction is different from the first direction. Method 700 is stopped at block 708.

In some embodiments, the first direction may be outward and the second direction may be inward. First places and second places can be based on various attributes or parameters, such as without limitation: geometric proximity to the central part of the reactor core 12, neutron flux so that the neutron flux in the first places is larger than the neutron flux in the second places, and ( or) reactivity so that k _effective in the first places is greater than k _effective . in second places.

In some other embodiments, the first direction may be inward and the second direction may be outward. Second places and first places can be based on various attributes or parameters, such as without limitation: geometric proximity to the central part of the reactor core 12, neutron flux so that the neutron flux in the second places is larger than the neutron flux in the first places, and ( or) reactivity so that k _effective in the second places is greater than k _effective in the first places.

Turning now to Fig. 8. In some embodiments, a method 800 is provided for controlling a traveling wave nuclear reactor. Method 800 begins at block 802. Turning further to FIG. 1B. At a block 804. at least one nuclear fission assembly 14 is moved in a first direction from a first place in a traveling wave nuclear reactor 12 to a second place in a traveling wave nuclear reactor 12. Second place is different from first place. At a block 806, a movement of at least one nuclear fission assembly 14 in a second direction from a second position is determined. The second direction is different from the first direction. Method 800 is stopped at block 808.

In some embodiments, the first direction may be outward and the second direction may be inward. First places and second places can be based on various attributes or parameters, such as without limitation: geometric proximity to the central part of the reactor core 12, neutron flux so that the neutron flux in the first places is larger than the neutron flux in the second places, and ( or) reactivity so that k _effective in the first places is greater than k _effective in the second places.

In some other embodiments, the first direction may be inward and the second direction may be outward, second places and first places may be based on various attributes or parameters, such as without limitation: geometric proximity to the central part of the reactor core 12, neutron flux as that the neutron flux in the second places is greater than the neutron flux in the first places, and (or) reactivity so that k _effective in the second places is greater than k _effective in the first places.

Turning now to Fig. 9. In some embodiments, a method 900 is provided for controlling a traveling wave nuclear reactor. Method 800 begins at block 902. Turning further to FIG. 1B. At a block 904, but at least one nuclear fission assembly 14 is moved in a first direction from a first place in a traveling wave nuclear reactor 12 to a second place in a traveling wave nuclear reactor 12. Second place is different from first place. At a block 906, at least one nuclear fission fuel assembly 14 is moved in a second direction from a second location. The second direction is different from the first direction. Method 900 is stopped at block 908.

In some embodiments, the first direction may be outward and the second direction may be inward. First places and second places can be based on various attributes or parameters, such as without limitation: geometric proximity to the central part of the reactor core 12, neutron flux so that the neutron flux in the first places is larger than the neutron flux in the second places, and ( or) reactivity so that k _effective in the first places is greater than k _effective in the second places.

In some other embodiments, the first direction may be inward and the second direction may be outward. Second places and first places can be based on various attributes or parameters, such as without limitation: geometric proximity to the central part of the reactor core 12, neutron flux so that the neutron flux in the second places is larger than the neutron flux in the first places, and ( or) reactivity so that k _effective in the second places is greater than k _effective in the first places.

Turning now to FIG. 10A. In some embodiments, a method 1000 is provided for controlling a traveling wave nuclear reactor. Method 1000 begins at block 1002. At block 1004, a predetermined burnup level is selected. At a block 1006, the movement of the selected nuclear fission fuel assemblies in the core of a nuclear reactor is determined so as to achieve a burnup level equal to a predetermined burnup level in virtually all nuclear fission fuel assemblies. Method 1000 is stopped at block 1008.

Turning further to FIG. 10B. In some embodiments, at block 1010, the selected nuclear fission fuel assemblies may be moved in the core of the nuclear fission reactor in accordance with the determined movement.

Turning further to FIG. 10C. In some embodiments, block 1012 may determine the extraction of the respective selected nuclear fission fuel assemblies when the burnup level is equal to a predetermined burnup level.

Turning further to FIG. 10D, in some embodiments, at block 1014, selected nuclear fission fuel assemblies may be removed in accordance with a specific extraction.

In the present application, formal headings are used for clarity of presentation. However, it should be understood that these headers serve the purposes of presentation, and that various types of subject matter can be considered in the application (for example, device (s) / structure (s) can be considered under the heading (s) of method (s) / operations, and (or) the method (s) / operations may be considered under the headings of a design (s) / process (s); and (or) descriptions of individual topics may cover two or more thematic headings). Therefore, the use of formal headings is not intended to limit the scope of the present invention in any way.

Specialists will understand that the above specific example methods and (or) devices and (or) technologies are representing more general methods and (or) devices and (or) technologies, the ideas of which are expressed elsewhere in the present description, such as in the claims filed together with this description, and (or) elsewhere in this application.

Experts know that the level of technology has reached a level at which a small difference remains between the implementation of aspects of the system with hardware, software, and (or) hardware and software; the use of hardware, software and / or firmware is usually (but not always, due to the fact that in some contexts the choice between hardware and software can become significant) is a design decision that represents a compromise between cost and effectiveness . Professionals know that there are various means by which processes and / or systems and / or other technologies described herein can be implemented (e.g., hardware, software, and / or firmware), and that a preferred means will vary depending on the context in which the processes and (or) systems and (or) other technologies are used. For example, if the person implementing the plan gives priority to speed and accuracy, he may be inclined mainly to a tool based on hardware and (or) software and hardware; alternatively, if flexibility is given priority, the person implementing the plan may be inclined mainly to implement software; or again alternatively, the person implementing the plan may be inclined to some combination of hardware, software, and (or) software and hardware. Therefore, there are several possible means by which the processes and (or) devices and (or) other technologies described in this document can be carried out, and none of the means is inherently superior to the other in the sense that any means for use represents a choice depending on the context in which this tool will be used, and the specific aspects (for example, speed, flexibility or predictability) that concern the person implementing the plan, any of which can vary Rova. It will be apparent to those skilled in the art that the optical aspects of the embodiments will typically use hardware, software, and / or optical-oriented hardware and software.

In some embodiments described herein, logical or similar implementations may include software control structures or other control structures. Electronic circuits, for example, may have one or more electric current paths constructed and arranged to perform various functions, as described herein. In some embodiments, one or more environments may be intended to carry an implementation detected by a device when these environments hold or transmit commands detected by a device intended to be executed as described herein. In some embodiments, for example, implementations may be updating or changing existing software, or firmware, or gate arrays, or programmable hardware, for example, by receiving or transmitting one or more commands in relation to one or more operations, described in this document. Alternatively or additionally, in some embodiments, the implementation may include components of special hardware, software, firmware, and / or universal components that execute or otherwise activate special components. Specifications or other implementations may be transmitted by one or more types of material transmission media, as described herein, optionally by packet transmission, or otherwise by passing through distributed media at different times.

Alternatively or additionally, implementations may include executing a special sequence of commands or activating circuits to enable, start, coordinate, query, or otherwise trigger one or more events of virtually any functional operations described herein. In some embodiments, operational or other logical descriptions herein may be expressed as source code and compiled or otherwise activated as an executable sequence of instructions. In some contexts, for example, implementations may be implemented, in whole or in part, by source code, such as C ++ code, or other code sequences. In other implementations, an implementation based on the source or code, being available in large numbers and (or) using well-known methods, can be compiled / implemented / translated / converted into a high-level descriptor language (for example, first the implementation of the described technologies in the programming language C or C ++ and then the transformation of the implementation in this programming language into the implementation in the language obtained by logical synthesis, the implementation in the hardware description language, the implementation by modeling anija hardware structure and (or) a similar way (s) of expression). For example, all or part of a logical expression (for example, an implementation in a programming language) can be performed as a hardware description in Verilog (for example, in a hardware description language (HDL) and / or in a hardware description language for ultrahigh-speed integrated circuits (VHDL) ) or as another circuit model, which can then be used to create a physical implementation that has hardware (for example, a specialized integrated circuit). Specialists will understand how to obtain, configure and optimize the appropriate transmitting and computing elements, material supplies, actuators or other designs in the light of these ideas.

The above description sets forth various embodiments of devices and / or processes using flow charts and / or examples. As far as these flowcharts and (or) examples contain one or more functions and (or) operations, specialists will understand that each function and / or operation on these flowcharts or in these examples can be implemented separately and (or) together a variety of hardware, types of software, software and hardware and / or almost any combination of them. In one embodiment, several parts of the subject matter described herein may be implemented using custom integrated circuits (ASICs), field programmable logic arrays (FPGAs), digital signal processing processors (DSPs), or other integrated formats. However, it is clear to those skilled in the art that certain aspects of the embodiments disclosed herein, in whole or in part, can equally be implemented in integrated circuits, as one or more computer programs run on one or more computers (for example, as one or more programs run on one or more computer systems), as one or more computer programs run on one or more processors (for example, as one or more programs run on one or more microprocessors), such as software and hardware, or almost any combination of them, and that the development of circuits and (or) writing code for software or software and hardware will be quite capable of specialists in the light of this disclosure. In addition, those skilled in the art will understand that the mechanisms of the subject invention described herein can be distributed as a software product in a variety of forms, and that the illustrative embodiment of the subject invention described herein is applicable regardless of the particular type of signal-carrying medium used for the actual implementation of the distribution. Examples of signal carrier media include, but are not limited to: rewritable media such as a floppy disk (floppy disk), hard disk, compact disc (CD), digital video disc (DVD), magnetic summer with digital information, computer memory, etc. .P.; and a transmission medium, such as a digital and / or analog communication medium (for example, a fiber optic cable, a waveguide, a wired channel, a wireless channel (for example, a transmitter, a receiver, transmission logic, reception logic, etc.) etc.

In a general sense, those skilled in the art will understand that the various aspects described herein that can be implemented — separately and (or) together — by various types of electromechanical systems having a wide variety of electrical components, such as hardware, software, hardware and software funds and (or) their almost any combination; and a variety of components that can apply mechanical force or impart movement, such as rigid bodies, spring or torsion bodies, hydraulic devices, devices with an electromagnetic drive and (or) almost any combination of them. Therefore, in the sense in which it is used in the present description, the term "electromechanical system" includes, without limitation, electrical circuits functionally connected to the transducer (for example, an actuator, an electric motor, a piezoelectric crystal, a microelectromechanical system (MEMS), etc. ), electrical circuits having at least one discrete electrical circuit, electrical circuits having at least one integrated circuit, electrical circuits having at least one s a specialized integrated circuit, electrical circuits forming a universal computing device configured by a computer program (for example, a universal computer configured by a computer program that at least partially implements the processes and / or devices described herein, or a microprocessor configured by a computer a program that at least partially implements the processes and (or) devices described herein), electrical circuits, about braziruemye storage device (for example, different types of memory (for example, random access memory, flash memory, read-only memory, etc.)), electrical circuits forming a communication device (for example, modem, communication switch (switch), optoelectric equipment and etc.) and (or) any non-electric analogue thereof, for example, optical or other analogs. Professionals will also understand that examples of an electromechanical system include, without limitation, a wide variety of household electronic equipment systems, medical devices, as well as other systems such as automobile transport systems, factory automation systems, security systems and / or communication / computing systems. Those skilled in the art will understand that, unless the context may dictate otherwise, the term “electromechanical”, as used in the present description, is not necessarily limited to a system having both an electric and a mechanical drive.

All the aforementioned US patents, publications of US patent applications, US patent applications, patents of other countries, patent applications of other countries and non-patent publications mentioned in the present description and (or) listed in any application data sheet (Application Data Sheet), link are included in the present description to the extent that they are consistent with it.

It will be apparent to those skilled in the art that the components described (eg, operations), devices, objects, and the discussion accompanying them are used as examples for clarity of concept, and that various modifications and changes to the design are possible. Therefore, the specific examples used in this document and the discussion that accompanies them are intended to represent their more general classes. In general, the use of any particular example is intended to represent its class, and not the inclusion of specific components (eg, operations), devices, and objects should not be construed as limiting the scope of the present invention.

As for the use in this document of virtually any terms in the plural and (or) singular, specialists can translate from the plural to the singular and (or) from the singular to the plural, as the context and (or) the application requires. For clarity, various permutations of the singular / plural are not explicitly provided herein.

The subject matter described herein sometimes illustrates various components contained in or associated with other components. It should be understood that these described architectures are purely exemplary, and that many other architectures that achieve the same functionality can actually be implemented. In a conceptual sense, any arrangement of components to achieve the same functionality is effectively “connected” so that the required functionality is achieved. Therefore, any two components in this document, combined to achieve a specific functionality, can be considered "interconnected" so that the desired functionality is achieved, regardless of architecture or intermediate components. Similarly, any two components connected in this way can be considered both “operationally connected” or “operationally linked” to achieve the required functionality, and any two components that can be connected in this way can also be considered as “capable of being interlocked with each other to achieve the required functionality. Specific examples of components that can be operationally coupled include, but are not limited to, physically mating and / or physically interacting components, and / or wirelessly interacting and / or wirelessly interacting components, and / or logically interacting and / or logically interacting Components.

Specific aspects of the subject matter described herein are shown and described above, but it is clear to those skilled in the art that, based on the above description, changes and modifications are possible within the spirit and scope of the subject of the present invention described herein and its broader aspects, and therefore, the appended claims should cover in their scope all of these changes and modifications within the spirit and scope of the subject matter of the present invention described herein. Those skilled in the art will understand that, in general, the terms used in this document, and especially in the attached claims (for example, in the text of the attached claims), are mostly intended as “open” terms (for example, the term “including” should be interpreted as “including without limitation”, the term “having” should be interpreted as “having at least”, the term “includes” should be interpreted as “includes without limitation”, etc.). In addition, it will be understood by those skilled in the art that if a specific h If the list of the items to be submitted is listed, this intention will be clearly indicated in the claims, and if there is no such listing, this intention is not available. "to represent a listing of items. However, the use of such phrases should not be construed as implying that the presentation of a listing of items with the indefinite articles" a "or" an "limits any a specific paragraph containing this listing of items presented, paragraphs containing only one such listing, even if the same paragraph includes introductory phrases “one or more” or “at least one” and indefinite articles such as “a” or “an "(for example," a "and (or)" an "should usually be interpreted as meaning" at least one "or" one or more "); the same applies to the use of certain articles used to introduce item enumerations. In addition, even the specific number of the enumeration of the items presented is really clearly mentioned, it is clear to specialists that this enumeration should usually be interpreted as meaning at least the indicated number (for example, a simple enumeration of “two enumerations” without other modifiers usually means at least two transfers or two or more transfers). In addition, in cases where an expression similar to “at least one of A, B and C, etc.,” is used, such a construction is usually intended in the sense in which one will understand this expression (for example, “system having at least one of A, B and C "will include, without limitation, systems having only A, only B, only C, A and B together, A and C together, B and C together and (or) A , B and C together, etc.). In cases where an expression similar to “at least one of A, B or C, etc.,” is used, such a construction is usually intended in the sense in which the specialist will understand this expression (for example, “a system having, by at least one of A, B or C "will include, without limitation, systems having only A, only B, only C, A and B together, A and C together, B and C together and (or) A, B and C together, etc.). In addition, those skilled in the art will understand that usually a disjunctive word and / or phrase representing two or more alternative terms, whether in the description, claims, or in the drawings, should be understood as suggesting the possibility of including one of these terms, any of these terms, or both terms, unless the context dictates otherwise. For example, the phrase “A or B” will usually be understood as including the capabilities of “A” or “B” or “A and B”.

As for the attached claims, those skilled in the art will understand that the operations listed therein can usually be performed in any order. In addition, although various operating flows are presented in a specific sequence (s), it should be understood that various operations may be performed in different orders than those illustrated or may be performed simultaneously. Examples of these alternative orders may include overlapping, alternating, interrupted, reordered, incremental, preparatory, additional, simultaneous, reverse, or other variant orders, unless the context dictates otherwise. In addition, terms such as “reacting to,” “referring to,” or other past tense adjectives are usually not intended to exclude these options unless the context dictates otherwise.

An aspect of the subject matter described herein is set forth in the following numbered paragraphs:

1. A method of operating a traveling wave nuclear reactor, comprising the following steps:

the stage at which the combustion front of the traveling wave of nuclear fission is distributed along the first and second measurements in several fuel subassemblies of nuclear fission in the active zone of a traveling wave nuclear reactor; and

the stage at which the selected several nuclear fission fuel subassemblies are controlled to be moved along the first measurement from the corresponding first places to the corresponding second places in such a way that the shape of the combustion front of the traveling nuclear fission wave along the second measurement is determined in accordance with the selected set of dimensional restrictions.

2. The method according to claim 1, where several of the fuel subassemblies of nuclear fission are elongated along the second dimension.

3. The method according to claim 1, where the first measurement is almost orthogonal to the elongated axis of several nuclear fission fuel subassemblies.

4. The method according to claim 1, where the first dimension and the second dimension are practically orthogonal to each other.

5. The method according to claim 1, where:

the first dimension includes a radial dimension; and

the second dimension includes an axial dimension.

6. The method according to claim 1, where:

the first dimension includes an axial dimension; and

the second dimension includes a radial dimension.

7. The method according to claim 1, where:

the first dimension includes an axial dimension: and the second dimension includes a lateral dimension.

8. The method according to claim 1, where:

the first dimension includes a lateral dimension; and the second dimension includes an axial dimension.

9. The method according to claim 1, where:

first places include outward places; and second places include inwardly directed places.

10. The method according to claim 9, where the inwardly directed places and the outwardly directed places are based on the geometric proximity to the central part of the reactor core.

11. The method according to claim 9, where the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

12. The method according to claim 9, where the inwardly directed places and the outwardly oriented places are based on reactivity so that k is _effective . inwardly directed places are greater than k _effective in outwardly directed places.

13. The method according to claim 1, where:

first places include inwardly directed places; and second places include outward places.

14. The method according to item 13, where the inwardly directed places and the outwardly directed places are based on the geometric proximity to the central part of the reactor core.

15. The method according to item 13, where the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

16. The method according to item 13, where the inwardly directed places and the outwardly directed places are based on reactivity such that k _effective in inwardly directed places is greater than k _effective in outwardly directed places.

17. The method according to claim 1, where the first places and second places are on opposite sides of the reference value along the first measurement.

18. The method according to claim 1, where the first places and second places include at least one attribute, which is almost equal.

19. The method according to p, where at least one attribute includes a geometric proximity to the Central region of the reactor core.

20. The method of claim 18, wherein the at least one attribute includes a neutron flux.

21. The method according to p. where at least one attribute includes reactivity.

22. The method according to claim 1, where the controlled movement of the selected multiple fuel subassemblies of nuclear fission along the first measurement from the corresponding first places to the corresponding second places includes the rotation of at least one of several selected multiple fuel subassemblies of nuclear fission.

23. The method according to claim 1, where the controlled movement of the selected multiple fuel subassemblies of nuclear fission along the first measurement from the respective first places to the corresponding second places includes turning over at least one of the selected several fuel subassemblies of nuclear fission.

24. The method according to claim 1, where the selected set of dimensional restrictions includes a predetermined maximum distance along the second dimension.

25. The method according to claim 1, where the selected set of dimensional restrictions is a function of at least one criterion of the combustion front.

26. The method according A.25, where the criterion of the combustion front includes a neutron flux.

27. The method according to p. where the neutron flux is associated with at least one of the selected several fuel subassemblies of nuclear fission.

28. The method according A.25, where the criterion of the combustion front includes a neutron fluence.

29. The method of claim 28, wherein the neutron fluence is coupled to at least one of several selected nuclear fission fuel subassemblies.

30. The method according A.25, where the criterion of the combustion front includes burnout.

31. The method according to clause 30, where the burnout is associated with at least one of the selected several fuel subassemblies of nuclear fission.

32. The method according to claim 25. where the criterion of the combustion front includes the location of the combustion front in at least one of several selected nuclear fission fuel subassemblies.

33. The method according to claim 1, where the controlled movement of the selected multiple nuclear fission fuel assemblies along the first measurement from the corresponding first places to the respective second places includes the controlled movement of the selected multiple nuclear fission fuel assemblies radially along the first measurement from the corresponding first places to the corresponding second places places.

34. The method according to claim 1. where the controlled movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places includes the controlled spiral movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places.

35. The method according to claim 1, where the controlled movement of the selected multiple fuel sub-assemblies of nuclear fission along the first measurement from the corresponding first places to the corresponding second places includes the controlled movement of the selected multiple fuel sub-assemblies of nuclear fission axially along the first measurement from the corresponding first places to the corresponding second places.

36. The method according to claim 1, where the shape of the combustion front of the traveling wave of nuclear fission is practically spherical.

37. The method according to claim 1. where the shape of the combustion front of the traveling wave of nuclear fission practically corresponds to the continuously selected curved surface.

38. The method according to claim 1, where the shape of the combustion front of the traveling wave of nuclear fission is practically axisymmetric with respect to the second dimension.

39. The method according to claim 1. where the shape of the combustion front of the traveling wave of nuclear fission has almost n-fold axial symmetry relative to the second dimension.

40. The method according to claim 1, where the shape of the combustion front of the traveling wave of nuclear fission along the second dimension is asymmetric.

41. The method according to clause 40. where the shape of the combustion front of the traveling wave of nuclear fission is axisymmetric with respect to the second dimension.

42. The method according to claim 1, further comprising the step of initiating a combustion front of the traveling nuclear fission wave by several assemblies of the igniter of the traveling nuclear fission wave.

43. The method according to § 42, further comprising a step in which at least one of several assemblies of the nuclear fission traveling wave igniter is extracted before the controlled movement of selected several nuclear fission fuel assemblies along the first measurement from the corresponding first places to corresponding second places.

44. The method according to item 43, where the extraction of at least one of several assemblies igniter of the traveling wave of nuclear fission before the controlled movement of the selected multiple fuel subassemblies of nuclear fission along the first measurement from the corresponding first places to the corresponding second places includes removing at least one from several assemblies of the igniter of the traveling wave from second places before the controlled movement of the selected several fuel subassemblies of nuclear fission along the first measurement from stvuyuschih first places in respective second seats.

45. The method according to claim 1, further comprising the step of causing the traveling wave nuclear reactor to become subcritical before the controlled movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places.

46. The method of claim 45, wherein causing the traveling wave nuclear reactor to become subcritical includes introducing neutron absorbing material into the reactor core.

47. The method according to item 45. including also the stage at which criticality is restored after the controlled movement of selected several nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places.

48. The method according to item 47. where the restoration of criticality includes the removal of at least part of the neutron-absorbing material from the reactor core.

49. The method of claim 45, further comprising the step of stopping the traveling wave nuclear reactor before the controlled movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places.

50. The method of claim 49, further comprising the step of restarting the traveling wave nuclear reactor after a controlled movement of selected multiple nuclear fission fuel subassemblies along the first measurement from the respective first places to corresponding second places.

51. A method for controlling a traveling wave nuclear reactor, comprising the following steps:

the stage at which for the combustion front of the traveling wave of nuclear fission propagating along the first and second measurements, determine the desired shape of the combustion front of the traveling wave of nuclear fission along the second dimension in several nuclear fission fuel subassemblies in accordance with the selected set of dimensional restrictions; and

the stage at which the movement of the selected several nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places is determined depending on the desired shape.

52. The method according to 51. including also the stage at which: determine the existing shape of the combustion front of the traveling wave of nuclear fission.

53. The method according to paragraph 51. where the determination of the movement of the selected multiple nuclear fission fuel assemblies along the first measurement from the corresponding first places to the corresponding second places, depending on the desired shape, includes the determination of the movement of the selected multiple nuclear fission fuel assemblies along the first measurement from the corresponding first places to the corresponding second places so. to set the desired shape.

54. The method of claim 51, wherein determining the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places, depending on the desired shape, includes determining the movement of the selected multiple nuclear fission nuclear fuel subassemblies along the first measurement from the corresponding first places in the corresponding second places so. to keep fit.

55. The method according to 51, also comprising a stage in which:

determine the time when to move the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

56. The method of claim 51, further comprising the step of:

move the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

57. The method of claim 51, wherein the multiple nuclear fission fuel subassemblies are elongated along the second dimension.

58. The method of claim 51, wherein the first measurement is substantially orthogonal to the elongated axis of several nuclear fission fuel subassemblies.

59. The method of claim 51, wherein the first dimension and the second dimension are substantially orthogonal to each other.

60. The method according to 51, where:

the first dimension includes a radial dimension; and

the second dimension includes an axial dimension.

61. The method according to 51, where:

the first dimension includes an axial dimension; and

the second dimension includes a radial dimension.

62. The method according to 51, where:

the first dimension includes an axial dimension; and

the second dimension includes a lateral dimension.

63. The method according to and 51, where:

the first dimension includes a lateral dimension: and

the second dimension includes an axial dimension.

64. The method according to 51, where:

first places include outward places; and

second places include inward-facing places.

65. The method according to claim 64, wherein the inwardly directed and the outwardly directed places are based on the geometric proximity to the central part of the reactor core.

66. The method according to item 64. where the inwardly directed places and the outwardly directed places are based on a neutron flux like this. that the neutron flux in inwardly directed places is greater than the neutron flux in outwardly directed places.

67. The method according to clause 64, where the inwardly directed places and the outwardly directed places are based on a reactivity such that k _effective "inwardly directed places are greater than k _effective in outwardly directed places.

68. The method according to 51, where:

first places include inwardly directed places; and

second places include outward places.

69. The method according to p, where the inwardly directed places and the outwardly directed places are based on the geometric proximity to the central part of the reactor core.

70. The method according to p, where the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

71. The method of claim 68, wherein the inwardly directed places and the outwardly directed places are based on reactivity such that k _effective in inwardly directed places is greater than k _effective in outwardly directed places.

72. The method according to § 51, where the first places and second places can be on opposite sides of the reference value along the first dimension.

73. The method according to § 51, where the first places and second places include at least one attribute, which is almost equal.

74. The method according to p, where at least one attribute includes a geometric proximity to the Central region of the reactor core.

75. The method according to p, where at least one attribute includes a neutron flux.

76. The method according to p, where at least one attribute includes reactivity.

77. The method of claim 51, wherein determining the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the respective first places to the corresponding second locations includes determining the rotation of at least one of the selected multiple nuclear fission fuel subassemblies.

78. The method according to 51. where the determination of the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the respective first places to the corresponding second locations includes determining the at least one of the selected multiple nuclear fission fuel subassemblies to flip.

79. The method of claim 51, wherein the selected set of dimensional constraints includes a predetermined maximum distance along the second dimension.

80. The method according to 51, where the selected set of dimensional restrictions is a function of at least one criterion of the combustion front.

81. The method according to p. 80, where the criterion of the combustion front includes a neutron flux.

82. The method of claim 81, wherein the neutron flux is associated with at least one of several selected nuclear fission fuel subassemblies.

83. The method of claim 80, wherein the burning front criterion comprises neutron fluence.

84. The method of claim 83, wherein the neutron fluence is coupled to at least one of several selected nuclear fission fuel subassemblies.

85. The method according to p. 80, where the criterion of the combustion front includes burnout.

86. The method of claim 85, wherein the burnout is associated with at least one of several selected nuclear fission fuel subassemblies.

87. The method according to p. 80, where the criterion of the combustion front includes the place of the combustion front in at least one of several selected nuclear fission fuel subassemblies.

88. The method of claim 51, wherein determining the movement of the selected multiple nuclear fission fuel assemblies along the first measurement from the corresponding first places to the second places includes determining the radial movement of the selected multiple nuclear fission fuel assemblies along the first measurement from the corresponding first places to the corresponding second places places.

89. The method of claim 51, wherein determining the movement of the selected multiple nuclear fission fuel assemblies along the first measurement from the corresponding first places to the second places includes determining the spiral movement of the selected multiple nuclear fission fuel assemblies along the first measurement from the corresponding first places to the corresponding second places places.

90. The method of claim 51, wherein determining the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the respective first places to the corresponding second locations includes determining an axial movement of the selected multiple nuclear fission fuel subassemblies.

91. The method according to 51, where the determination of the desired shape of the combustion front of the traveling wave of nuclear fission includes determining the practically spherical shape of the combustion front of the traveling wave of nuclear fission.

92. The method of claim 51, wherein determining a desired shape of a burning front of a traveling wave of nuclear fission along a second dimension includes determining the shape of a continuously curved surface of a burning front of a traveling wave of nuclear fission.

93. The method according to 51, where the desired shape of the combustion front of the traveling wave of nuclear fission is practically axisymmetric with respect to the second dimension.

94. The method according to 51, where the desired shape of the combustion front of the traveling wave of nuclear fission has almost n-fold axial symmetry relative to the second dimension.

95. The method according to 51, where the desired shape of the combustion front of the traveling wave of nuclear fission is asymmetric.

96. The method according to p, where the desired shape of the combustion front of the traveling wave of nuclear fission is axisymmetric with respect to the second dimension.

97. A system comprising:

for the burning front of a nuclear fission traveling wave propagating along the first and second measurements, the first electrical circuits designed to determine the desired shape of the burning front of a nuclear fission traveling wave along the second dimension in several fuel subassemblies of nuclear fission in accordance with the selected set of dimensional restrictions: and

second electrical circuits designed to determine the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

98. The system of claim 97, wherein the second electrical circuits are also designed to determine the existing shape of the combustion front of a traveling wave of nuclear fission.

99. The system of claim 97, wherein the second circuitry is also for determining the movement of selected multiple nuclear fission fuel subassemblies along the first measurement from the respective first locations to the corresponding second locations so as to establish the desired shape.

100. The system of claim 97, wherein the second electrical circuits are also for determining the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first locations to the corresponding second locations so as to maintain the desired shape.

101. The system of claim 97, wherein the second electrical circuits are also intended to determine the time when to move the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

102. The system of claim 97, wherein the multiple nuclear fission fuel subassemblies are elongated along the second dimension.

103. The system of claim 97, wherein the first measurement is substantially orthogonal to the elongated axis of several nuclear fission fuel subassemblies.

104. The system of claim 97, wherein the first dimension and the second dimension are substantially orthogonal to each other.

105. The system of claim 97, wherein:

the first dimension includes a radial dimension; and

the second dimension includes an axial dimension.

106. The system of claim 97, wherein:

the first dimension includes an axial dimension: and

the second dimension includes a radial dimension.

107. The system of claim 97, wherein:

the first dimension includes an axial dimension; and

the second dimension includes a lateral dimension.

108. The system of claim 97, wherein:

the first dimension includes a lateral dimension; and

the second dimension includes an axial dimension.

109. The system of claim 97, wherein:

first places include outward places; and

second places include inward-facing places.

110. The system of claim 109, wherein the inwardly directed places and the outwardly directed places are based on the geometric proximity to the central part of the reactor core.

111. The system of claim 109, wherein the inwardly directed places and the outwardly directed places are based on a neutron flux as follows. that the neutron flux in inwardly directed places is greater than the neutron flux in outwardly directed places.

112. The system of claim 109, wherein the inwardly directed places and the outwardly directed places are based on reactivity such that k _effective in inwardly directed places is greater than k _effective in outwardly directed places.

113. The system of claim 97, wherein:

first places include inwardly directed places; and

second places include outward places.

114. The system of claim 113, wherein the inwardly directed and the outwardly oriented places are based on the geometric proximity to the central part of the reactor core.

115. The system of claim 113, wherein the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

116. The system of claim 113, wherein the inwardly directed places and the outwardly directed places are based on reactivity such that k _effective in inwardly directed places is greater than k _effective in outwardly directed places.

117. The system of claim 97, wherein the first places and second places are on opposite sides of the reference value along the first dimension.

118. The system of claim 97, wherein the first places and second places include at least one attribute that is substantially equal.

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

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

121. The system of claim 118, wherein the at least one attribute includes reactivity.

122. The system of claim 97, wherein the second electrical circuits are also designed to determine the rotation of at least one of the selected multiple nuclear fission fuel subassemblies.

123. The system of claim 97, wherein the second electrical circuits are also designed to determine the inversion of at least one of the selected multiple nuclear fission fuel subassemblies.

124. The system of claim 97, wherein the selected set of dimensional constraints includes a predetermined maximum distance along the second dimension.

125. The system of claim 97, wherein the selected set of dimensional constraints is a function of at least one criterion of the combustion front.

126. The system according to p, where the criterion of the combustion front includes a neutron flux.

127. The system of claim 126. where the neutron flux is associated with at least one of the selected several fuel subassemblies of nuclear fission.

128. The system of claim 125, wherein the criterion of the combustion front includes neutron fluence.

129. The system of claim 128, wherein the neutron fluence is associated with at least one of several selected nuclear fission fuel subassemblies.

130. The system according to p, where the criterion of the combustion front includes burnout.

131. The system of claim 130, wherein the burnup is associated with at least one of a selected multiple nuclear fission fuel subassemblies.

132. The system according to p. 125, where the criterion of the combustion front includes the place of the combustion front in at least one of several selected nuclear fission fuel subassemblies.

133. The system of claim 97, wherein the second electrical circuits are also intended for determining the radial movement of selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places.

134. The system of claim 97, wherein the second electrical circuits are also designed to determine the spiral movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places.

135. The system of claim 97, wherein the second electrical circuits are also for determining axial displacement of selected multiple nuclear fission fuel subassemblies.

136. The system according to p. 97, where the first electrical circuits are designed to determine the almost spherical shape of the combustion front of the traveling wave of nuclear fission.

137. The system of claim 97, wherein the first electrical circuits are also designed to determine the shape of a continuously curved surface of the combustion front of a traveling nuclear fission wave.

138. The system of claim 97, wherein the desired shape of the combustion front of the traveling wave of nuclear fission is practically axisymmetric with respect to the second dimension.

139. The system of claim 97, wherein the desired shape of the combustion front of the traveling wave of nuclear fission has almost n-fold axial symmetry with respect to the second dimension.

140. The system of claim 97, wherein the desired shape of the combustion front of the traveling wave of nuclear fission is asymmetric.

141. The system of claim 140, wherein the desired shape of the combustion front of the traveling wave of nuclear fission is axisymmetric with respect to the second dimension.

142. A computer program product comprising:

the first control program on a computer-readable medium designed to determine, for the combustion front of a traveling nuclear fission wave propagating along the first and second measurements, the desired shape of the combustion front of a traveling nuclear fission wave along the second measurement in several nuclear fission fuel subassemblies in accordance with the selected set of dimensional restrictions: and

the second control program on a computer-readable medium, designed to determine the movement of the selected several nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

143. The computer program product according to p, where the second control program on a computer-readable medium is also intended to determine the existing shape of the combustion front of a traveling nuclear fission wave.

144. The computer program product according to p. 142, where the second control program on a computer-readable medium is designed to determine the movement of the selected several nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places as follows. to set the desired shape.

145. The computer program product according to p, where the second control program on a computer-readable medium is designed to determine the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places so. to keep fit.

146. The computer program product according to p, where the second control program on a computer-readable medium is also used to determine the time when to move the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

147. The computer program product according to p, where several of the fuel subassemblies of nuclear fission are elongated along the second dimension.

148. The computer program product according to p, where the first measurement is practically orthogonal to the elongated axis of several nuclear fission fuel subassemblies.

149. The computer program product according to p, where the first dimension and the second dimension are almost orthogonal to each other.

150. The computer program product according to p, where:

the first dimension includes a radial dimension; and

the second dimension includes an axial dimension.

151. The computer software product according p, where:

the first dimension includes an axial dimension; and

the second dimension includes a radial dimension.

152. The computer software product according p, where:

the first dimension includes an axial dimension; and

the second dimension includes a lateral dimension.

153. The computer software product according p, where:

the first dimension includes a lateral dimension; and

the second dimension includes an axial dimension.

154. The computer software product according p, where:

first places include outward places; and

second places include inward-facing places.

155. A computer software product according to p. 154. where the inwardly directed and outwardly directed places are based on the geometric proximity to the central part of the reactor core.

156. The computer program product of claim 154, wherein the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

157. The computer program product of claim 154, wherein the inwardly directed places and the outwardly directed places are based on reactivity such that k _effective in inwardly directed places is greater than k _effective in outwardly directed places.

158. The computer software product according p, where:

first places include inwardly directed places; and

second places include outward places.

159. The computer program product of claim 158, wherein the inwardly directed and the outwardly directed places are based on the geometric proximity to the central part of the reactor core.

160. The computer program product of claim 158, wherein the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

161. The computer program product of claim 158, wherein the inwardly directed places and the outwardly directed places are based on reactivity such that k _effective in inwardly directed places is greater than k _effective in outwardly oriented places.

162. The computer program product according to p, where the first places and second places can be located on opposite sides of the reference value along the first measurement.

163. The computer program product of claim 142, wherein the first places and second places include at least one attribute that is substantially equal.

164. The computer program product according to p, where at least one attribute includes a geometric proximity to the Central region of the reactor core.

165. The computer program product according to p, where at least one attribute includes a neutron flux.

166. The computer program product according to p, where at least one attribute includes reactivity.

167. The computer program product according to p, where the second circuitry is designed to determine the rotation of at least one of the selected multiple fuel subassemblies of nuclear fission.

168. The computer program product according to p, where the second circuitry is designed to determine the inversion of at least one of the selected multiple fuel subassemblies of nuclear fission.

169. The computer software product according to p. where the selected set of dimensional constraints includes a predetermined maximum distance along the second dimension.

170. The computer program product according to p, where the selected set of dimensional restrictions is a function of at least one criterion of the combustion front.

171. The computer software product according p, where the criterion of the combustion front includes a neutron flux.

172. The computer program product according to Claim 171, wherein the neutron flux is associated with at least one of several selected nuclear fission fuel subassemblies.

173. The computer software product of claim 170, wherein the burning front criterion includes neutron fluence.

174. The computer program product according to Claim 173, wherein the neutron fluence is associated with at least one of several selected nuclear fission fuel subassemblies.

175. The computer program product of claim 170, wherein the criterion of a combustion front includes burn-out.

176. The computer program product according to Claim 175, wherein the burnout is associated with at least one of several selected nuclear fission fuel subassemblies.

177. The computer program product according to p, where the criterion of the combustion front includes the location of the combustion front in at least one of the selected multiple fuel subassemblies of nuclear fission.

178. The computer program product according to p, where the second control program on a computer-readable medium includes a third control program on a computer-readable medium, designed to determine the radial movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places.

179. The computer program product according to p. 142, where the second control program on a computer-readable medium includes a fourth control program on a computer-readable medium, designed to determine the spiral movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places.

180. The computer program product according to p, where the second control program on a computer-readable medium includes a fifth control program on a computer-readable medium, designed to determine the axial displacement of selected several nuclear fission fuel subassemblies.

181. The computer program product according to p, where the first control program on a computer-readable medium includes a seventh control program on a computer-readable medium, designed to determine the practically spherical shape of the combustion front of a traveling nuclear fission wave.

182. The computer program product according to p, where the first control program on a computer-readable medium includes an eighth control program on a computer-readable medium designed to determine the shape of a continuously curved surface of the combustion front of a traveling nuclear fission wave.

183. The computer program product according to p, where the desired shape of the combustion front of the traveling wave of nuclear fission is practically axisymmetric with respect to the second dimension.

184. The computer program product according to p, where the desired shape of the combustion front of the traveling wave of nuclear fission has almost n-fold axial symmetry relative to the second dimension.

185. The computer software product according to p. 142. where the desired shape of the combustion front of the traveling wave of nuclear fission is asymmetric.

186. The computer program product according to p, where the desired shape of the combustion front of the traveling wave of nuclear fission is axisymmetric with respect to the second dimension.

187. A system comprising:

for the combustion front of a traveling nuclear fission wave propagating along the first and second measurements, the first electrical circuits designed to determine the desired shape of the combustion front of a traveling nuclear fission wave along the second dimension in several fuel subassemblies of nuclear fission in accordance with the selected set of dimensional restrictions;

second electrical circuits designed to determine the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape; and

a subassembly designed to move selected multiple nuclear fission fuel subassemblies responsive to second electrical circuits.

188. The system of claim 188, wherein the second electrical circuits are also intended to determine the existing shape of the combustion front of a traveling wave of nuclear fission.

189. The system of claim 188, wherein the second electrical circuits are also for determining the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first locations to the corresponding second locations so as to establish the desired shape.

190. The system of claim 187. where the second electrical circuits are designed to determine the movement of the selected multiple fuel subassemblies of nuclear fission along the first measurement from the corresponding first places to the corresponding second places so as to maintain the desired shape.

191. The system of claim 188, wherein the second electrical circuits are also designed to determine time. when to move the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

192. The system of claim 188, wherein the multiple nuclear fission fuel subassemblies are elongated along the second dimension.

193. The system of claim 188, wherein the first measurement is substantially orthogonal to the elongated axis of several nuclear fission fuel subassemblies.

194. The system according to and. 187, where the first dimension and the second dimension are substantially orthogonal to each other.

195. The system of claim 187, wherein:

the first dimension includes a radial dimension; and

the second dimension includes an axial dimension.

196. The system of claim 187, wherein:

the first dimension includes an axial dimension; and

the second dimension includes a radial dimension.

197. The system of claim 187, wherein:

the first dimension includes an axial dimension; and

the second dimension includes a lateral dimension.

198. The system of claim 187, wherein:

the first dimension includes a lateral dimension; and

the second dimension includes an axial dimension.

199. The system of claim 187, wherein:

first places include outward places; and

second places include inward-facing places.

200. The system of claim 199, wherein the inwardly directed places and the outwardly directed places are based on the geometric proximity to the central part of the reactor core.

201. The system of claim 199, wherein the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

202. The system of claim 199, wherein the inwardly directed places and the outwardly directed places are based on reactivity as follows. that k _effective and inwardly directed places are greater than k _effective in outwardly directed places.

203. The system of claim 187, wherein:

first places include inwardly directed places; and

second places include outward places.

204. The system of claim 203, wherein the inwardly directed and the outwardly directed places are based on the geometric proximity to the central part of the reactor core.

205. The system of claim 203, wherein the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

206. The system of claim 203, wherein the inwardly directed places and the outwardly directed places are based on reactivity such that k _effective in inwardly directed places is greater than k _effective in outwardly directed places.

207. The system of claim 187, wherein the first places and second places may be on opposite sides of the reference value along the first dimension.

208. The system of claim 188, wherein the first places and second places include but at least one attribute that is substantially equal.

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

210. The system of claim 208, wherein the at least one attribute includes a neutron flux.

211. The system of claim 208, wherein the at least one attribute includes reactivity.

212. The system of claim 188, wherein the second electrical circuits are also designed to determine the rotation of at least one of the selected multiple nuclear fission fuel subassemblies.

213. The system of claim 188, wherein the second electrical circuits are also intended to determine the inversion of at least one of the selected multiple nuclear fission fuel subassemblies.

214. The system of claim 187. where the subassembly includes a nuclear fuel handling device.

215. The system of claim 188, wherein the subassembly is also intended for radial movement of selected multiple nuclear fission fuel subassemblies from corresponding first places to corresponding second places.

216. The system of claim 188, wherein the subassembly is also intended for the helical movement of selected several nuclear fission fuel subassemblies from corresponding first places to corresponding second places.

217. The system of claim 187. where the subassembly is also intended for axial movement of selected several nuclear fission fuel subassemblies.

218. The system of claim 188, wherein the subassembly is also intended to rotate selected several nuclear fission fuel subassemblies.

219. The system of claim 187. where the subassembly is also intended to flip selected several nuclear fission fuel subassemblies.

220. A traveling wave nuclear reactor comprising: an active zone of a traveling wave nuclear reactor;

several fuel fission subassemblies of nuclear fission received in the active zone of a nuclear reactor on a traveling wave, each of several fuel fission subassemblies of nuclear fission designed to propagate the combustion front of the traveling nuclear fission wave along the first and second dimensions:

first electrical circuits designed to determine the desired shape of the combustion front of a traveling wave of nuclear fission along the second dimension in several fuel subassemblies of nuclear fission in accordance with the selected set of dimensional restrictions;

second electrical circuits designed to determine the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape; and

a subassembly designed to move selected multiple nuclear fission fuel subassemblies responsive to second electrical circuits.

221. The reactor according to claim 220, wherein the second electrical circuits are also designed to determine the existing shape of the combustion front of a traveling nuclear fission wave.

222. The reactor according to claim 220, wherein the second electrical circuits are also intended for determining the movement of selected several nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places as follows. to set the desired shape.

223. The reactor according to claim 220, wherein the second electrical circuits are also designed to determine the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places so as to maintain the desired shape.

224. The reactor according to claim 220, wherein the second electrical circuits are also used to determine the time when to move the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

225. The reactor according to claim 220, wherein several of the nuclear fission fuel subassemblies are elongated along the second dimension.

226. The reactor according to claim 220, wherein the first measurement is substantially orthogonal to the elongated axis of several nuclear fission fuel subassemblies.

227. The reactor of claim 220, wherein the first dimension and the second dimension are substantially orthogonal to each other.

228. The reactor according to claim 220. Where:

the first dimension includes a radial dimension; and

the second dimension includes an axial dimension.

229. The reactor according to claim 220, where:

the first dimension includes an axial dimension; and

the second dimension includes a radial dimension.

230. The reactor according to claim 220, where:

the first dimension includes an axial dimension; and

the second dimension includes a lateral dimension.

231. The reactor according to claim 220, where:

the first dimension includes a lateral dimension; and

the second dimension includes an axial dimension.

232. The reactor according to claim 220, where:

first places include outward places; and

second places include inward-facing places.

233. The reactor according to claim 232, wherein the inwardly directed and outwardly directed places are based on the geometric proximity to the central part of the reactor core.

234. The reactor according to p. 232, where the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

235. The reactor according to claim 232, wherein the inwardly directed places and the outwardly directed places are based on reactivity such that k _effective in inwardly directed places is greater than k _effective in outwardly directed places.

236. The reactor according to claim 220. Where:

first places include inwardly directed places; and

second places include outward places.

237. The reactor according to claim 233, wherein the inwardly directed and outwardly directed places are based on the geometric proximity to the central part of the reactor core.

238. The reactor according to claim 233, wherein the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

239. The reactor of claim 236, wherein the inwardly directed and the outwardly oriented sites are based on reactivity such that k is _effective . inwardly directed places are greater than k _effective in outwardly directed places.

240. The reactor according to claim 220. where the first places and second places can be on opposite sides of the reference value along the first dimension.

241. The reactor according to p, where the first places and second places include at least one attribute, which is almost equal.

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

243. The reactor according to p. 241. where at least one attribute includes a neutron flux.

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

245. The reactor according to claim 220. where the second electrical circuits are designed to determine the rotation of at least one of the selected several fuel subassemblies of nuclear fission.

246. The reactor according to p. 220, where the second electrical circuits are designed to determine the inversion of at least one of the selected several fuel subassemblies of nuclear fission.

247. The reactor according to claim 220, wherein the selected set of dimensional constraints includes a predetermined maximum distance along the second dimension.

248. The reactor according to claim 220, wherein the selected set of dimensional constraints is a function of at least one criterion of the combustion front.

249. The reactor according to paragraph 248, where the criterion of the combustion front includes a neutron flux.

250. The reactor according to p. 249, where the neutron flux is associated with at least one of the selected several fuel subassemblies of nuclear fission.

251. The reactor according to paragraph 248, where the criterion of the combustion front includes the neutron fluence.

252. The reactor according to claim 251, wherein the neutron fluence is associated with at least one of several selected nuclear fission fuel subassemblies.

253. The reactor according to paragraph 248, where the criterion of the combustion front includes burnout.

254. The reactor according to and. 253, where burnup is associated with at least one of several selected nuclear fission fuel subassemblies.

255. The reactor according to paragraph 248, where the criterion of the combustion front includes the location of the combustion front in at least one of several selected fuel subassemblies of nuclear fission.

256. The reactor according to p. 220, where the second electrical circuit is designed to determine the radial movement of the selected multiple fuel subassemblies of nuclear fission along the first measurement from the corresponding first places to the corresponding second places.

257. The reactor according to claim 220, wherein the second electrical circuits are also intended for determining the helical movement of the selected several nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places.

258. The reactor according to claim 220, wherein the second electrical circuits are also intended to determine the axial displacement of selected several nuclear fission fuel subassemblies.

259. The reactor according to claim 220, where the first electrical circuits are also designed to determine the almost spherical shape of the combustion front of a traveling wave of nuclear fission.

260. The reactor according to claim 220, wherein the first electrical circuits are also intended to determine the shape of the continuously curved surface of the combustion front of a traveling nuclear fission wave.

261. The reactor according to claim 220, where the desired shape of the combustion front of the traveling wave of nuclear fission is practically axisymmetric with respect to the second dimension.

262. The reactor according to p. 220, where the desired shape of the combustion front of the traveling wave of nuclear fission has almost n-fold axial symmetry relative to the second dimension.

263. The reactor according to claim 220, where the desired shape of the combustion front of the traveling wave of nuclear fission is asymmetric.

264. The reactor according to p. 263, where the desired shape of the combustion front of the traveling wave of nuclear fission is axisymmetric with respect to the second dimension.

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

266. The reactor according to claim 220, wherein the subassembly is also intended for radial movement of selected several nuclear fission fuel subassemblies from corresponding first places to corresponding second places.

267. The reactor according to claim 220, wherein the subassembly is also intended for the helical movement of selected several nuclear fission fuel subassemblies from the corresponding first places to the corresponding second places.

268. The reactor according to claim 220, wherein the subassembly is also intended for axial movement of selected several nuclear fission fuel subassemblies.

269. The reactor according to claim 220, wherein the subassembly is also intended for rotation of selected several nuclear fission fuel subassemblies.

270. The reactor according to claim 220, wherein the subassembly is also intended for inverting selected several nuclear fission fuel subassemblies.

271. A method of operating a traveling-wave nuclear reactor, comprising the following steps:

a stage in which at least one fuel assembly of nuclear fission is moved outward from the first place in the active zone of the traveling wave nuclear reactor to the second place in the active zone of the traveling wave nuclear reactor

272. The method according to p. 271, which also includes a stage in which at least one fuel assembly of nuclear fission is moved inward from the second place.

273. The method according to p. 271, where the first places and second places are based on the geometric proximity to the central part of the reactor core.

274. The method according to p. 271, where the first places and second places are based on the neutron flux so that the neutron flux in the first places is greater than the neutron flux in the second places.

275. The method according to clause 271, where the first places and second places are based on reactivity so that k_effective in the first places more than k_effective in second places.

276. A method of operating a traveling wave nuclear reactor, comprising the following steps:

a stage in which the movement of at least one fuel assembly of nuclear fission in the first direction from the first place in the active zone of the traveling wave nuclear reactor to the second place in the active zone of the traveling wave nuclear reactor is determined, the second place being different from the first place; and

a stage in which the movement of at least one fuel assembly of nuclear fission in the second direction from the second place is determined, the second direction being different from the first direction.

277. The method according to clause 276, where:

the first direction is outward; and

the second direction is inward.

278. The method according to clause 277, where the first places and second places are based on the geometric proximity to the Central part of the reactor core.

279. The method according to clause 277, where the first places and second places are based on the neutron flux so that the neutron flux in the first places is greater than the neutron flux in the second places.

280. The method according to clause 277, where the first places and second places are based on reactivity as follows. that k _effective in the first places is greater than k _effective in the second places.

281. The method according to clause 276, where:

the first direction is inward; and

the second direction is outward.

282. The method according to p. 281, where the second places and first places are based on the geometric proximity to the Central part of the reactor core.

283. The method according to p, where the second places and first places are based on the neutron flux so that the neutron flux in the second places is greater than the neutron flux in the first places.

284. The method of claim 281, wherein the second places and first places are based on reactivity such that k _effective in second places is greater than k _effective in first places.

285. A method of operating a traveling-wave nuclear reactor, comprising the following steps:

a stage in which at least one fuel assembly of nuclear fission is moved in the first direction from the first place in the active zone of the traveling wave nuclear reactor to the second place in the active zone of the traveling wave nuclear reactor, the second place being different from the first place; and

a stage in which the movement of at least one fuel assembly of nuclear fission in the second direction from the second place is determined, the second direction being different from the first direction.

286. The method according to p. 285, where:

the first direction is outward; and

the second direction is inward.

287. The method according to p. where the first places and second places are based on the geometric proximity to the central part of the reactor core.

288. The method according to p. 286, where the first places and second places are based on the neutron flux so that the neutron flux in the first places is greater than the neutron flux in the second places.

289. The method according to p. 286, where the first places and second places are based on reactivity so that k _effective in the first places is greater than k _effective in the second places.

290. The method according to p. 285, where:

the first direction is inward; and

the second direction is outward.

291. The method according to p, where the second places and first places are based on the geometric proximity to the Central part of the reactor core.

292. The method according to p, where the second places and first places are based on the neutron flux so that the neutron flux in the second places is greater than the neutron flux in the first places.

293. The method according to p, where the second places and first places are based on reactivity so that k _effective in second places is greater than k _effective in first places.

294. A method of operating a traveling-wave nuclear reactor, comprising the following steps:

a stage in which at least one fuel assembly of nuclear fission is moved in the first direction from the first place in the active zone of the traveling wave nuclear reactor to the second place in the active zone of the traveling wave nuclear reactor, the second place being different from the first place; and

a stage in which at least one fuel assembly of nuclear fission is moved in the second direction from the second place, the second direction being different from the first direction.

295. The method according to p. 294, where:

the first direction is outward; and

the second direction is inward.

296. The method according to p. 295, where the first places and second places are based on the geometric proximity to the Central part of the reactor core.

297. The method according to p. 295, where the first places and second places are based on the neutron flux so that the neutron flux in the first places is greater than the neutron flux in the second places.

298. The method according to p. 295, where the first places and second places are based on reactivity so that k _effective in the first places is greater than k _effective in the second places.

299. The method according to p. 294, where:

the first direction is inward; and

the second direction is outward.

300. The method according to p, where the second places and first places are based on the geometric proximity to the Central part of the reactor core.

301. The method according to p, where the second places and first places are based on the neutron flux so that the neutron flux in the second places is greater than the neutron flux in the first places.

302. The method according to p, where the second places and the first places are based on reactivity so that k _effective in the second places is greater than k _effective in the first places.

303. A method of operating a nuclear fission reactor, comprising the following stages:

a stage at which a predetermined burnup level is selected; and

the stage at which the movement of the selected several nuclear fission fuel assemblies in the core of the nuclear reactor is determined so as to achieve a burnup level equal to a predetermined burnup level in virtually all nuclear fission fuel assemblies.

304. The method according to p. 303, also including a stage in which:

the selected multiple nuclear fission fuel assemblies are moved to the core of the nuclear fission reactor in accordance with the determined movement.

305. The method according to claim 304, further comprising the step of: determining the extraction of the respective selected multiple nuclear fission fuel assemblies when the burnup level is equalized to a predetermined burnup level.

306. The method according to p. 305, which also includes a stage in which the selected multiple fuel assemblies of nuclear fission are extracted in accordance with a specific extraction in accordance with a specific extraction.

Various aspects and embodiments are disclosed herein, however, other aspects and embodiments will be apparent to those skilled in the art. The various aspects and embodiments disclosed herein are for purposes of illustration and are not intended to limit the scope of the present invention, the scope and spirit of the present invention being indicated by the following claims.

Claims (44)

1. A method of operating a traveling-wave nuclear reactor, comprising the following steps:
the stage at which the combustion front of the traveling wave of nuclear fission is distributed along the first and second measurements in several fuel subassemblies of nuclear fission in the active zone of a traveling wave nuclear reactor; and
the stage at which the selected several nuclear fission fuel subassemblies are controlled to be moved along the first measurement from the corresponding first places to the corresponding second places in such a way that the shape of the combustion front of the traveling nuclear fission wave along the second measurement is determined in accordance with the selected set of dimensional restrictions;
moreover, the controlled movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places includes the controlled movement of the selected multiple nuclear fission fuel subassemblies radially and helically along the first measurement from the corresponding first places to the corresponding second places. 2. The method of claim 1, wherein the multiple nuclear fission fuel subassemblies are elongated along the second dimension. 3. The method of claim 1, wherein the first measurement is substantially orthogonal to the elongated axis of several nuclear fission fuel subassemblies. 4. The method of claim 1, wherein the first dimension and the second dimension are substantially orthogonal to each other. 5. The method of claim 1, wherein the first measurement includes a radial measurement and the second measurement includes an axial measurement. 6. The method of claim 1, wherein the first measurement includes an axial measurement and the second measurement includes a radial measurement. 7. The method of claim 1, wherein the first measurement includes an axial measurement and the second measurement includes a lateral measurement. 8. The method of claim 1, wherein the first measurement includes a lateral measurement and the second measurement includes an axial measurement. 9. The method of claim 1, wherein the first places include outwardly directed places and the second places include inwardly directed places. 10. The method according to claim 1, where the first places include inwardly directed places and the second places include outwardly directed places. 11. The method according to claim 1, where the first places and second places can be on opposite sides of the reference value along the first dimension. 12. The method according to claim 1, where the first places and second places include at least one attribute, which is almost equal. 13. The method according to p. 12, where at least one attribute includes an attribute selected from geometrical proximity to the Central region of the reactor core, neutron flux and reactivity. 14. The method of claim 1, wherein the controlled movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the respective first locations to the corresponding second locations includes rotating at least one of several selected nuclear fission fuel subassemblies. 15. The method of claim 1, wherein the controlled movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the respective first locations to the corresponding second locations includes turning over at least one of several selected nuclear fission fuel subassemblies. 16. The method of claim 1, wherein the selected set of dimensional constraints includes a predetermined maximum distance along the second dimension. 17. The method according to claim 1, where the selected set of dimensional restrictions is a function of at least one criterion of the combustion front. 18. The method according to p. 17, where the criterion of the combustion front includes a neutron flux. 19. The method according to p. 18, where the neutron flux is associated with at least one of the selected several fuel subassemblies of nuclear fission. 20. The method according to p. 17, where the criterion of the combustion front includes neutron fluence. 21. The method according to p. 20, where the neutron fluence is associated with at least one of the selected several fuel subassemblies of nuclear fission. 22. The method according to p. 17, where the criterion of the combustion front includes burnout. 23. The method according to p. 22, where the burnout is associated with at least one of the selected several fuel subassemblies of nuclear fission. 24. The method according to p. 17, where the criterion of the combustion front includes the location of the combustion front in at least one of the selected several fuel subassemblies of nuclear fission. 25. The method of claim 1, wherein the controlled movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the second places includes the controlled movement of the selected multiple nuclear fission fuel subassemblies axially along the first measurement from the corresponding first places to the corresponding second places places. 26. The method according to claim 1, where the definition of the desired shape includes a shape selected from a mainly spherical shape of the combustion front of a traveling nuclear fission wave, a shape corresponding to a continuously selected curved surface, a shape practically axisymmetric with respect to the second dimension, and a shape having almost n-fold axial symmetry relative to the second dimension. 27. The method according to claim 1, where the shape of the combustion front of the traveling wave of nuclear fission along the second dimension is asymmetric. 28. The method according to p. 27, where the shape of the combustion front of the traveling wave of nuclear fission is axisymmetric with respect to the second dimension. 29. The method of claim 1, further comprising the step of initiating a combustion front of a traveling nuclear fission wave by several assemblies of a traveling nuclear fission wave igniter. 30. The method of claim 29, further comprising the step of: at least one of several assemblies of the nuclear fission traveling wave igniter being removed before the controlled movement of the selected multiple nuclear fission fuel assemblies along the first measurement from the corresponding first places to corresponding second places. 31. The method according to p. 30, where the extraction of at least one of the several assemblies igniter of the traveling wave of nuclear fission before the controlled movement of the selected multiple fuel subassemblies of nuclear fission along the first measurement from the corresponding first places to the corresponding second places includes removing at least one from several assemblies of the igniter of the traveling wave from second places before the controlled movement of the selected several fuel subassemblies of nuclear fission along the first measurement from existing first places to the corresponding second places. 32. The method of claim 1, further comprising the step of causing the traveling wave nuclear reactor to become subcritical before the controlled movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places. 33. The method of claim 32, wherein causing the traveling wave nuclear reactor to become subcritical includes introducing neutron absorbing material into the reactor core. 34. The method according to p. 32, which also includes the stage at which criticality is restored after the controlled movement of the selected several nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places. 35. The method according to p. 34, where the restoration of criticality includes the removal of at least part of the neutron-absorbing material from the reactor core. 36. The method according to p. 32, which also includes the stage at which the traveling wave nuclear reactor is stopped before the controlled movement of selected several nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places. 37. The method of claim 36, further comprising the step of restarting the traveling wave nuclear reactor after a controlled movement of selected multiple nuclear fission fuel subassemblies along the first measurement from the respective first places to corresponding second places. 38. The method according to any one of paragraphs. 9 and 10, where the first and second inwardly directed places and outwardly directed places are based on at least one attribute selected from a geometrical proximity to the central part of the reactor core, the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in outward places, and reactivity so that k _effective in inward places are greater than k _effective in outward places. 39. A method of operating a traveling wave nuclear reactor, comprising the following steps:
a stage in which at least one fuel assembly of nuclear fission is moved outward from the first place in the active zone of the traveling wave nuclear reactor to the second place in the active zone of the traveling wave nuclear reactor;
moreover, the controlled movement of at least one nuclear fission fuel assembly outward from a first place in a traveling wave nuclear reactor to a second place in a traveling wave nuclear reactor includes a controlled movement of said at least one nuclear fission fuel assembly spirally along a first dimension from said first place to said second place. 40. The method according to claim 39, where the first and second places are based on at least one attribute selected from the geometrical proximity to the central part of the reactor core, the neutron flux so that the neutron flux in the first places is greater than the neutron flux in the second places , and reactivity so that k _effective in the first places is greater than k _effective in the second places. 41. The method according to p. 40, which also includes a stage in which at least one fuel assembly of nuclear fission is moved inward from the second place. 42. A method of operating a nuclear fission reactor, comprising the following stages:
a stage at which a predetermined burnup level is selected; and
the stage at which the movement of the selected several nuclear fission fuel assemblies in the core of the nuclear reactor is determined so as to achieve a burn-out level equal to a predetermined burn-out level in almost all nuclear fission fuel assemblies;
a stage in which the selected multiple nuclear fission fuel assemblies are moved in the core of the nuclear fission reactor in accordance with the determined movement;
moreover, the specified movement in accordance with a specific movement includes the movement of the selected multiple fuel assemblies of nuclear fission radially and spirally along the first measurement from the corresponding first places to the corresponding second places. 43. The method of claim 42, further comprising the step of determining the extraction of the respective selected multiple nuclear fission fuel assemblies when the burnup level is equal to a predetermined burnup level. 44. The method of claim 43, further comprising the step of selecting the selected multiple nuclear fission fuel assemblies in accordance with a specific extraction.

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