CN102714066B - The method and system of fuel assembly is migrated in fission-type reactor - Google Patents

The method and system of fuel assembly is migrated in fission-type reactor Download PDF

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Publication number
CN102714066B
CN102714066B CN201080060902.4A CN201080060902A CN102714066B CN 102714066 B CN102714066 B CN 102714066B CN 201080060902 A CN201080060902 A CN 201080060902A CN 102714066 B CN102714066 B CN 102714066B
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dimension
fission
subassembly
fission fuel
row ripple
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CN102714066A (en
Inventor
E.格林斯潘
R.A.海德
R.C.佩特罗斯基
J.C.沃尔特
T.A.威佛
C.惠特默
小劳威尔.L.伍德
G.B.齐默尔曼
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TerraPower LLC
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TerraPower LLC
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Priority claimed from US12/590,448 external-priority patent/US10008294B2/en
Priority claimed from US12/657,735 external-priority patent/US9786392B2/en
Priority claimed from US12/657,726 external-priority patent/US9799416B2/en
Priority claimed from US12/657,725 external-priority patent/US9922733B2/en
Application filed by TerraPower LLC filed Critical TerraPower LLC
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
    • G21C19/205—Interchanging of fuel elements in the core, i.e. fuel shuffling
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • G21C1/022—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders characterised by the design or properties of the core
    • G21C1/026—Reactors not needing refueling, i.e. reactors of the type breed-and-burn, e.g. travelling or deflagration wave reactors or seed-blanket reactors
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/001—Computer implemented control
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Abstract

Exemplary embodiments provides and migrates the method and system of fuel assembly, the method for operation nuclear fission row ripple reactor, the method for nuclear fission row ripple reactor that controls, the system of control nuclear fission row ripple reactor in fission-type reactor, controls the computer software program product of nuclear fission row ripple reactor and the nuclear fission row ripple reactor of the system with migration fuel assembly.

Description

The method and system of fuel assembly is migrated in fission-type reactor
Technical field
The present invention relates to migrate the method and system of fuel assembly in fission-type reactor.
Background technology
Cross
The application relates to application listed below (" related application ") and requires to obtain from application listed below Obtaining the earliest can by the rights and interests of live application day (such as, it is desirable to can using the earliest of non-provisional is preferential Quan, or require temporary patent application, and any and all parent of related application, Zu Fudai, once Grandfather generation etc. application based on 35USC § 119(e) rights and interests).Appointing of related application and related application All themes that what and all parents, Zu Fudai, great grandfather's generation etc. apply for will not be with this with such theme The degree that the theme of literary composition is inconsistent is herein incorporated by reference.
Related application
For the non-legal requirements of U.S.Patent & Trademark Office (USPTO), the application constitutes 2009 11 Month submission on the 6th, inventor Ehud Greenspan, Roderick A.Hyde, Robert C.Petroski, Joshua C.Walter、Thomas Allan Weaver、Charles Whitmer、Lowell L.Wood,Jr.、 With George B.Zimmerman, invention entitled " METHODS AND SYSTEMS FOR MIGRATING FUEL ASSEMBLIES IN A NUCLEAR FISSION REACTOR(is at core Fission reactor migrates the method and system of fuel assembly) " U.S. Patent Application No. 12/590,448 Part continuation application, this application is the most co-pending, or gives current co-pending application with Shen Please the application of rights and interests of day.
For the non-legal requirements of U.S.Patent & Trademark Office (USPTO), the application constitutes 2010 1 Month submission on the 25th, inventor Ehud Greenspan, RoderickA.Hyde, Robert C.Petroski, Joshua C.Walter、Thomas Allan Weaver、Charles Whitmer、Lowell L.Wood,Jr.、 With George B.Zimmerman, invention entitled " METHODS AND SYSTEMS FOR MIGRATING FUEL ASSEMBLIES IN A NUCLEAR FISSION REACTOR(is at core Fission reactor migrates the method and system of fuel assembly) " U.S. Patent Application No. 12/657,725 Part continuation application, this application is the most co-pending, or gives current co-pending application with Shen Please the application of rights and interests of day.
For the non-legal requirements of U.S.Patent & Trademark Office (USPTO), the application constitutes 2010 1 Month submission on the 25th, inventor Ehud Greenspan, RoderickA.Hyde, Robert C.Petroski, Joshua C.Walter、Thomas Allan Weaver、Charles Whitmer、Lowell L.Wood,Jr.、 With George B.Zimmerman, invention entitled " METHODS AND SYSTEMS FOR MIGRATING FUEL ASSEMBLIES IN A NUCLEAR FISSION REACTOR(is at core Fission reactor migrates the method and system of fuel assembly) " U.S. Patent Application No. 12/657,726 Part continuation application, this application is the most co-pending, or gives current co-pending application with Shen Please the application of rights and interests of day.
For the non-legal requirements of U.S.Patent & Trademark Office (USPTO), the application constitutes 2010 1 Month submission on the 25th, inventor Ehud Greenspan, RoderickA.Hyde, Robert C.Petroski, Joshua C.Walter、Thomas Allan Weaver、Charles Whitmer、Lowell L.Wood,Jr.、 With George B.Zimmerman, invention entitled " METHODS AND SYSTEMS FOR MIGRATING FUEL ASSEMBLIES IN A NUCLEAR FISSION REACTOR(is at core Fission reactor migrates the method and system of fuel assembly) " U.S. Patent Application No. 12/657,735 Part continuation application, this application is the most co-pending, or gives current co-pending application with Shen Please the application of rights and interests of day.
The computer program requirement of the most issued USPTO that come into force of U.S.Patent & Trademark Office (USPTO) Patent applicant quotes sequence number and whether instruction application is the continuation application of parent application, part continuation application Or the bulletin of divisional application.Relevant content refers to Stephen G.Kunin, Benefit of Prior-Filed Application, USPTO Official Gazette March 18,2003.The applicant's entity is (referred to hereinafter as For " applicant ") quote being provided above as described in regulation the specific of application requiring its priority. The applicant understands, this regulation is clear and definite its specific quoting on language, it is not necessary to serial number or picture " continue Continuous " or " part continues " as any sign carry out the priority of requirement U.S. Patent application.Although such as Mentioned above, but the applicant understands, and the computer program of USPTO has some data entry requirement, because of This applicant provides the appointment of the relation between the application described above and its parent application, but Ying Ming Really pointing out, such appointment must not be understood as in addition to the theme of its parent application, and whether the application Any types of comments of comprising certain new theme and/or recognize.
Summary of the invention
Exemplary embodiments provides and migrates the method and system of fuel assembly, behaviour in fission-type reactor The method making nuclear fission row ripple reactor, the method controlling nuclear fission row ripple reactor, control nuclear fission row The system of ripple reactor, control the computer software program product of nuclear fission row ripple reactor and with moving Move the nuclear fission row ripple reactor of the system of fuel assembly.
Summary above is merely an illustrative, and is never intended to limit by any way the present invention.Remove Outside above-mentioned exemplary aspect, embodiment and feature, by with reference to accompanying drawing and detailed further below, Further aspect, embodiment and feature will be made to become apparent.
Accompanying drawing explanation
Figure 1A is the block diagram of the exemplary methods of operation nuclear fission row ripple reactor；
Figure 1B-1D is the perspective view of the partially schematic form of the parts of exemplary fission-type reactor reactor core；
Fig. 1 E-1H migrating nuclear fission row ripple burnfront exemplified with selected fission fuel subassembly The impact of shape；
Fig. 1 I is the block diagram of the details of the part of the method for Figure 1A；
Fig. 1 J is exemplified with the rotation of fission fuel subassembly；
Fig. 1 K is the block diagram of the details of the part of the method for Figure 1A；
Fig. 1 L overturning exemplified with fission fuel subassembly；
Fig. 1 M-1N is the block diagram of the details of the part of the method for Figure 1A；
Fig. 1 O migrates exemplified with the spiral of fission fuel subassembly；
Fig. 1 P is the block diagram of the details of the part of the method for Figure 1A；
Fig. 1 Q is exemplified with the axial migration of fission fuel subassembly；
Fig. 1 R is approximately spherical exemplified with nuclear fission row ripple burnfront；
Fig. 1 S is exemplified with the continuous bend surface of nuclear fission row ripple burnfront；
Fig. 1 T is exemplified with the substantially non-rotational symmetric shape of nuclear fission row ripple burnfront；
Fig. 1 U-1V is exemplified with the substantially n fold rotational symmetry of the shape of nuclear fission row ripple burnfront；
Fig. 1 W is exemplified with the asymmetrical shape of nuclear fission row ripple burnfront；
Fig. 1 X-1AF is the block diagram of the details of the part of the method for Figure 1A；
Fig. 2 A is the block diagram of the exemplary methods controlling nuclear fission row ripple reactor；
Fig. 2 B-2M is the block diagram of the details of the part of the method for Fig. 2 A；
Fig. 3 A determines that the block diagram of the illustrative system of the migration of fission fuel subassembly；
Fig. 3 B-3C is the block diagram of the details of the parts of the system of Fig. 3 A；
Fig. 4 A is the block diagram of the illustrative system migrating fission fuel subassembly；
Fig. 4 B-4C is the block diagram of the details of the parts of the system of Fig. 4 A；
Fig. 5 is the block diagram of the partially schematic form of exemplary nuclear fission row ripple reactor；
Fig. 6 A is the flow chart of the exemplary methods of operation nuclear fission row ripple reactor；
Fig. 6 B is the block diagram of the details of the part of the method for Fig. 6 A；
Fig. 7 is the flow chart of the exemplary methods of operation nuclear fission row ripple reactor；
Fig. 8 is the flow chart of the exemplary methods of operation nuclear fission row ripple reactor；
Fig. 9 is the flow chart of the exemplary methods of operation nuclear fission row ripple reactor；
Figure 10 A is the flow chart of the exemplary methods of operation nuclear fission row ripple reactor；
Figure 10 B-10D is the block diagram of the details of the part of the method for Figure 10 A；
Detailed description of the invention
In the following detailed description, with reference to the accompanying drawing forming its part.In the accompanying drawings, similarity sign is usual Mark similar component, unless otherwise indicated by context.It is described in detailed description, accompanying drawing and claim Being not intended to limit property of exemplary embodiments in book.Can be without departing from the essence of the theme shown here Utilize other embodiments to god or scope, and may be made that other changes.
Exemplary embodiments provides and migrates the method and system of fuel assembly, behaviour in fission-type reactor The method making nuclear fission row ripple reactor, the method controlling nuclear fission row ripple reactor, control nuclear fission row The system of ripple reactor, control the computer software program product of nuclear fission row ripple reactor and with moving Move the nuclear fission row ripple reactor of the system of fuel assembly.
Nuclear fission row ripple is summarized
Before the explanation details about non-limiting example given herein, relevant nuclear fission will be provided The brief overview of row ripple.Although nuclear fission row ripple is also referred to as nuclear fission deflagration wave, but for clarity, Refer to nuclear fission row ripple herein.As discussed below some parts includes the information taken passages from following paper: Entitled " Completely Automated Nuclear Power Reactors For Long-Term Operation:III.Enabling Technology For Large-Scale,Low-Risk,Affordable Nuclear Electricity ", author is Edward Teller, Muriel Ishikawa, Lowell Wood, Roderick Hyde and John Nuckolls, is presented on the Workshop of the Aspen in July, 2003 Global Change Institute,University of California Lawrence Livermore National (this paper prepares to submit to Laboratory publication UCRL-JRNL-122708 (2003)Energy, The International Journal, 30November 2003), hereby it is incorporated by reference in it Hold.
The reactor core of nuclear fission row ripple reactor is being moved past with the speed of the annual about one cm order of magnitude In " ripple ", convertible fission fuel regeneration fissionable nucleus fission fuel, then fissionable nucleus fission Fuel experience fission.
For be used in nuclear fission row ripple reactor some fission fuel imagined without limitation as (my god So, dilution or concentrate) uranium, thorium, plutonium or even before burned fission fuel assemblies such, The most broadly available.Can also use without limitation as other actinides or its isotope Other less widely available fission fuel.Some nuclear fission row ripple reactors intend full power ground for a long time Run about 1/3rd century to about 1/2nd century or the order of magnitude of longer time.Some nuclear fission row ripples react Heap is not intended to change nuclear fuel (and being intended to emergency burial during noeud vital phase bundle), but some other nuclear fissions Row ripple reactor intends to change nuclear fuel, and some change nuclear fuel and occur during shutdown that some change nuclear fuel and send out Raw during operation at power.It is also intended to avoid fission fuel to reprocess in some cases, from And reduce the probability turning to military use and other problem.
Realize not changing nuclear fuel ground Operation at full power 1/3-1/2 century (or longer time) and avoiding core to split While becoming fuel reprocessing, compatible hope allows to need to use fast neutron spectrum.Additionally, nuclear fission row Ripple is propagated and is allowed to reach the high average burn-up of non-concentrated actinium series fuel as natural uranium or thorium, and Less " the nuclear fission ignition of the appropriate isotopic enrichment of fissionable nucleus material is used in the loading area of reactor core Device " region.
So, nuclear fission row ripple reactor core can suitably include that nuclear fission igniter and relatively macronucleus split Become detonation combustion wave propagation regions.Nuclear fission detonation combustion wave propagation regions suitably comprises thorium or uranium fuel, And work according to the General Principle of fast neutron spectrum fission propagation.
In order to the utilization of effective fission fuel and the requirement to enriched isotope are minimum, make nuclear fission row ripple anti- Answering heap reactor core is suitable multiplier (-icator).Further, fast neutron spectrum is suitably used, because not removing fission product, Fission product generally makes thorium to the big absorption cross-section of thermal neutron, or in uranium fuel embodiment, more rich uranium Isotope238The fuel of U is not fully utilized.
Will now describe exemplary nuclear fission row ripple.Detonation combustion wave is permissible by the propagation of fission fuel Release is it is contemplated that the power of level.If additionally, as finding in typical commercial power generation nuclear reactor Configuration such, material configuration has a sufficient time invariant features, then produce may for thing followed power It is on maintenance level.Finally, if row velocity of wave propagation can be regulated with practical way from outside, then Energy release rate can be controlled as desired, therefore control power and produce.
The nucleonics of nuclear fission row ripple is described below.Absorb the neutron induction actinides-can of any energy The selected isotopic nuclear fission of fission element may make in any material temperature including any low temperature Release nuclear-binding energy.The neutron that fissible actinides absorbs can be provided by nuclear fission igniter.
The isotopic nuclear fission of substantially any actinium series is to averagely often absorbing in each neutron release more than one Son, can provide the chance dissipating neutron mediation nuclear fission chain reaction in such material.Generally, The neutron population every time absorbing release is expressed as η, wherein η=υ σf/(σf+σc), υ is fission release every time Neutron population.The each neutron (on average, in certain neutron energy scope) absorbed discharges more than two First individual neutron may make the atom of not fissionable isotope be converted into fissible same by primary neutron capture Position element (via neutron absorption and β decay subsequently), then, additionally makes the former of newly generated fissionable isotope Neutron fission is there is in daughter nucleus during second time neutron fission absorbs.
If on average, from given nuclear fission event a neutron can the most fissible but " can Conversion " on atomic nucleus by radiation capture, this most fissible but " convertible " atomic nucleus be then converted into (as Via β decay like that) it is converted into fissionable atom core, and second neutron from identical fission event Can be captured on fissionable atom core, thus induced fission, then can be by most of high Z(Z >=90) Nucleic is used as the fission fuel material in row ripple reactor (or breeder reactor).Especially, if this A little any one arranged are all steady statues, then can meet propagation nuclear fission row ripple in given material Sufficient condition.
Due to isotopic β decay middle during convertible consideration convey is changed into fissionable nucleus, make fission material Material can be used for the ratio of fission and is restricted.Therefore, the characteristic velocity that wavefront enters was by several days or some months number The half-life of magnitude limits.Such as, the characteristic velocity that wavefront enters can with the order of magnitude of such ratio, in The distance that the sub fission birth from it is advanced to its radiation capture on convertible core is (i.e., averagely certainly By journey) decay partly the declining of (the MaLS atomic nucleus in chain) with the β becoming fissionable nucleus from convertible core The ratio of phase.For majority of case interested, in normal density actinium series, such feature is split Become neutron transport distance approximation 10cm, and the β decay half-life is 105-106Second.Then, some are set Meter, characteristic wave speed is 10-4-10-7cm/s.Such speed that is relatively advanced slowly shows, can be by ripple Sign is embarked on journey ripple (traveling wave) or deflagration wave (deflagration wave) rather than detonation wave (detonation wave).
If row ripple attempts to accelerate, then its forward position can run into the purest fertile material (from neutron For in the sense that, lose relatively large) because the concentration of the fissionable nucleus before ripple center becomes to refer to Number declines.Therefore, the forward position (hereinafter referred to as " burnfront ") of ripple is slow or slowly.On the contrary, If ripple is slow, and conversion ratio is remained above 1(it is to say, the rate of increase is more than fission rate), then by even The local concentration of the fissionable nucleus that continuous β decay causes increases.The local velocity of fission and generation neutron rises, And the forward position of ripple, i.e. burnfront accelerates.
Finally, if all parts of the configuration of the initial convertible material sufficiently rapidly propagated from ripple Remove the heat being associated with nuclear fission, although during then propagation can occur in arbitrarily low material temperature The temperature of son and fissioning nucleus can be about 1MeV(million electro-volt).
So cause and propagate the condition of nuclear fission row ripple and can utilize and can be readily available material and realize.Though So the fissionable isotope of actinides with regard to absolute and relative in the fertile isotope of these elements for, It is rare on land, but can concentrate, concentrate and synthesize fissionable isotope.Such as, initially Fission chain reaction uses picture respectively233U、235U and239As Pu natural and artificial fissible with Position element is well-known.
The consideration hint of relevant neutron cross section, if the neutron spectra in ripple is " firmly " or " soon " neutron spectra, Then nuclear fission row ripple can burn picture232Th or238As U, the reactor core of natural actinides is the biggest Part.If fissioning broken it is to say, the neutron carrying out chain reaction in ripple has from new life with them Approximation 1MeV being evaporated in sheet is compared, and is not the least energy, then, when the office of fission product (one mole fissible is recalled when portion's quality share is suitable with the local quality share of fertile material Material fission is converted into the fission-product nucleus of two moles), local space time's neutron economy can be avoided relatively Big loss.Even have desired hot properties, as Ta typical neutron reactor structural material Neutron is lost in≤and the neutron energy of 0.1MeV also becomes the biggest.
Another kind of consider to be neutron multiplication rate v of the fission with incident neutron energy and cause fission (and not Be only that the gamma-rays that causes of neutron absorption is launched) all neutron-absorbing events share α (relatively Little) change.The algebraic symbol of function alpha (v-2) constitutes every kind of fissionable isotope for reactor core, Not from reactor core leakage neutron or the situation that absorbs (as on fission product) at its endobiosis Under, in the fertile material suitable with total fissionable isotope mass budget, propagation nuclear fission row ripple can The condition of row.For can drop to institute's thoughts in resonance capture region from the fission neutron of approximation 1MeV Interest fissionable isotope, this algebraic symbol is typically all positive.
Amount alpha (v-2)/v be total fission produce neutron be expert at ripple propagate during may because of leakage, parasitic absorption, Geometric divergence and the upper limit of share lost.Note actual interested all having for generally occurring in Imitating the great majority in the neutron energy scope (approximation 0.1-1.5MeV) in the configuration of non-slowing down actinides can Fissile isotope, this share is 0.15-0.30.Generally deposit with for the neutron of (surpassing) thermal energy Situation contrary, the parasitic loss wherein caused by fission product ratio can be switched to that of fissible conversion High 1-1.5 the decimal number magnitude of a little loss, convertible coordination in neutron energy scope 0.1-1.5MeV The fissionable element of element capture generates captures excellent 0.7-1.5 the order of magnitude than fission product.The former implies in heat Can be switched to fissible conversion on or near neutron energy and only can reach degree feasible, then of 1.5-5% Person represents, for nearly disintegration energy neutron spectra, it is contemplated that the conversion more than 50%.
When considering the condition propagating nuclear fission row ripple, in some means, for very big, " self-reflection " Actinides configures, and can effectively marginalize out neutron leakage.It will be understood that can distinguish the most relative Two kinds of abundant actinidess:232Th and238The uniqueness of U natural thorium and uranium and main (MaLS) The sufficiently large configuration of isotopic composition is set up row ripple propagate.
Specifically, fission neutron transporting in these actinium series isotopes is likely to result at neutron energy Drop significantly to below 0.1MeV (easily capture on fission-product nucleus with non-inappreciable probability therewith Obtain) before, the capture on fertile isotope core or the fission of fissionable isotope core.It will be understood that Fission product nuclear concentration can close to or exceed convertible nuclear concentration in some cases, and fissionable nucleus is dense Spend and keeping quantity simultaneously quite reliably, can be less than the smaller of fission product or convertible core The order of magnitude.The consideration hint in relevant neutron scattering cross section, fully extends in their radial dimension and makes There is for fission neutron effective infinite thickness it is to say, the configuration of actinides of self-reflection To have > 200gm/cm2(gram per centimeter2) density-radius product it is to say, they will have238U-232Th density of solid > > radius of 10-20cm.
Propagation and combustion wave provide superfluous neutron, go out to become 1-2 mean free path internal breeding The new fissile material of unburned fuel, is effectively substituted in fissionable fuel burned in ripple.Combustion wave Peak " lime-ash " below is substantially " neutron is neutral ", because the neutron reaction of its fission fraction Just balanced by the fission product storage of the parasitic absorption of structure and leakage top.If ripple center and just Along with ripple, to propagate be that the time is static to fissionable atom storage before it, then can the most so, If it is less, ripple " dead "；And if it is greater, then it is believed that ripple " accelerates ".
Therefore, in the isotopic configuration of natural actinium series can with long interval of time under basic limit Propagate and keep nuclear fission row ripple.
Above discussion considers the diameter natural uranium less than about a meter or thorium gold by non-limitative example Belong to cylinder, if application can make nuclear fission row ripple stably propagate arbitrarily long axial distance effective in Sub-reflector, then can make diameter much smaller.But, the propagation of nuclear fission row ripple only should not be construed It is limited to cylinder, symmetrical geometry, or simply connected geometry.To this end, be described in the following literature nuclear fission The additional embodiment of the alternative geometry of row ripple reactor core: submit on November 28th, 2006, invent Artificial RODERICK A.HYDE, MURIEL Y.ISHIKAWA, NATHAN P. MYHRVOLD and LOWELL L.WOOD, JR., invention entitled " AUTOMATED NUCLEAR POWER REACTOR FOR LONG-TERM OPERATION " United States Patent (USP) Apply for the 11/605th, No. 943, be hereby incorporated by reference into its content.
The embodiment to nuclear fission row ripple reactor of propagating of nuclear fission row ripple has Suggestion.As first Example, makes local material Temperature Feedback affect karyomerite with acceptable cost in ripple neutron economy of can being expert at Reaction rate.So big negative temperature coefficient of neutron reaction imparts the energy of the pace controlling row ripple Power.If extracting little thermal power from burning fuel, then its temperature rises and temperature-independent is reactive Decline, and the supercentral Fission Rate of ripple correspondingly diminishes and the equation of time of ripple only reflects the least axle March forward speed.Similarly, if thermal power removes speed greatly, material temperature declines and neutron reaction Rise, then in ripple, neutron economy becomes relative undamped, and ripple the most relatively rapidly advances.Have Pass can be incorporated to the details of the illustrative implementation of the Temperature Feedback in the embodiment of reactor core assembly and describe In the following literature: submission on November 28th, 2006, inventor RODERICK A.HYDE, MURIEL Y.ISHIKAWA, NATHAN P.MYHRVOLD and LOWELL L.WOOD, JR., invention entitled " CONTROLLABLE LONG TERM OPERATION OF A NUCLEAR REACTOR " U.S. Patent Application No. 11/605,933, be hereby incorporated by reference into Its content.
As the Suggestion propagating the embodiment to nuclear fission row ripple reactor of nuclear fission row ripple second Individual example, it is possible to use all or less than nuclear fission row ripple reactor in total fission neutron yield.Example As, without limitation as the neutron absorber material in control rod or local material-thermostatic module Reactivity control system, it is possible to use the total fission neutron yield in nuclear fission row ripple reactor 10 is about 5-10%.Additionally≤10% of total fission neutron yield in nuclear fission row ripple reactor may be in response to being used in core Fission row ripple reactor structure member in high-performance, high-temperature structural material (as Ta, W or Re that Sample) parasitic absorption and lose.Occur that this loss is desired in order to realize when being converted into electric energy Thermodynamic efficiency and obtain high security of system quality factor (figures-of-merit).As Ta, W or The Z value of Re these materials such is the approximation 80% of the Z value of actinides, therefore in their high energy Sub-radiative capture cross section is not the least compared with actinides.Total fission in nuclear fission row ripple reactor The final 5-10% of neutron yield may lose because of the parasitic absorption in fission product.However, it is possible to it is pre- Phase frequency spectrum may be similar to the frequency spectrum of sodium cooling fast reactor, because parasitic absorption may only account for the big of loss About 1-2%.As it has been described above, neutron economy is the abundantest, i.e. at not leakage and rapid geometry In the case of dissipating, the approximation 70% of total fission neutron yield be enough to maintain row ripple to propagate.
As the Suggestion propagating the embodiment to nuclear fission row ripple reactor of nuclear fission row ripple the 3rd Individual example, the high burnup as the initial actinium series fuel stock of the feature of nuclear fission row ripple (is up to about 20% To about 30%, in some cases, about 40% or 50% arrives the order of magnitude up to about 80%), can make Raw ore fuel efficiently utilized-additionally, without reprocessing.
Noting, the neutron flux from the strongest combustion zone after burnfront makes on burnfront forward position Fissible Feng Tongweisuqu breeds, thus is used for making nuclear fission row wavefront enter.Burning at nuclear fission row ripple After front skims over the fuel of given quality, generate the fission product of increasing quality carrying out fission While thing, as long as the neutron radiation capture on available convertible core is than the neutron irradiation on fission-product nucleus The most much, fissionable atom concentration continues to rise in capture.In any particular moment, core power Produce density peaks all in this loading area.
It will be understood that enter after burnfront far away from nuclear fission row wavefront, fission-product nucleus (put down by its quality All close to the half of fissionable nucleus) climbing with the concentration of fissionable nucleus ratio can be with fissible fission and fission The numerical value that the ratio of product radiative capture cross section is suitable." locally neutron reaction " therewith close to negative value, or In some embodiments, it may be possible to become negative value.Therefore, burn and breed and the most effectively stop.Also It will be understood that in certain embodiments, can add can not fission neutron as boron carbide, hafnium or gadolinium Absorbing material, is negative to ensure " locally neutron reaction ".
In some embodiments of nuclear fission row ripple reactor, install during manufacturing reactor core assembly The all fission fuel being once used in reactor.Additionally, in some configurations, never from reactor Reactor core assembly removes spentnuclear fuel.In a kind of means, such embodiment may make at nuclear fission point Run after burnfront has been propagated, with after fire and perhaps never accessing reactor core.
In some other embodiments of nuclear fission row ripple reactor, during manufacturing reactor core assembly All fission fuel that installation was once used in reactor, and in some configurations, never from reaction Heap reactor core assembly removes spentnuclear fuel.But, by as described below, can be in the difference of reactor in-core Between place or central migration or switch at least some fission fuel.Such at least some can be performed The migration of fission fuel or switch, to realize target as discussed below.
But, in some other embodiments of nuclear fission row ripple reactor, can nuclear fission ignition it After additional fission fuel is added in reactor core assembly.Nuclear fission row ripple reactor some its In its embodiment, can remove from reactor core assembly spentnuclear fuel (and, in certain embodiments, Removing spentnuclear fuel from reactor core assembly can be at nuclear fission row ripple reactor just at operation at power Carry out) simultaneously.Illustrate such exemplary refuelling and discharge of the fuel in the following literature: 2006 11 Month submission on the 28th, inventor RODERICK A.HYDE, MURIEL Y.ISHIKAWA, NATHAN P.MYHRVOLD and LOWELL L.WOOD, JR., invention entitled " METHOD AND SYSTEM FOR PROVIDING FUEL IN A NUCLEAR REACTOR " the U.S. Patent application the 11/605th, 848, is incorporated by reference into its content hereby.With whether remove spentnuclear fuel without Closing, the preexpanding of original-pack fuel makes along with nuclear fission row ripple skims over any to dead axle of actinium series " fuel " To element, convert thereof into fission product " lime-ash ", the cumulative volume of combustion elements will not be made to have any change Ground replaces the actinides of higher density with more low-density fission product.
Be given by general introduction, nuclear fission traveling wave launcher is arrived232Th or238U loading area can utilize non- Restrictively as rich in the fission fuel assemblies of fissionable isotope " nuclear fission ignition module " Start.In the following literature be discussed in detail launch nuclear fission row ripple exemplary nuclear fission ignition module and Method: submission on February 12nd, 2008, inventor CHARLES E.AHLFELD, JOHN ROGERS GILLELAND、RODERICK A.HYDE、MURIEL Y.ISHIKAWA、 DAVID G.MCALEES, NATHAN P.MYHRVOLD, CHARLES WHITMER and LOWELL L.WOOD, JR., invention entitled " NUCLEAR FISSION IGNITER " same Time Co-pending U.S. patent application the 12/069th, 908, be hereby incorporated by reference into its content.Higher is dense Contracting can produce compacter module, and minimum mass module can apply moderator Concentraton gradient.It addition, Nuclear fission ignition module can partly by as prevent material for transfer military purposes under various situations that The non-technical of sample considers to determine.
In other means, exemplary nuclear fission igniter can contain other type of reaction source.Such as, Other nuclear fission igniter can include " glowing embers ", such as, by propagating the reaction of nuclear fission row ripple The fission fuel rich in fissionable isotope in neutron it is exposed in heap.Despite the presence of various quantity Fission product " lime-ash ", but such " glowing embers " can play the effect of nuclear fission igniter.Sending out Penetrating in other means of nuclear fission row ripple, the nuclear fission ignition module that can will be enriched in fissionable isotope is used Energetic ion (picture element, deuteron, alpha-particle etc. are such) or the electricity of neutron may be produced again in supplementary use Other neutron source in the electric drive source of son.In a kind of exemplary means, can by as linear accelerator that The particle accelerator of sample is positioned to high energy proton being supplied to and can be provided that, such neutron (such as, passes through Spallation) intermediate materials.In another kind of exemplary means, can be by grain as linear accelerator Sub-accelerator is positioned to high energy electron being supplied to and can be provided that, such neutron is (such as, by high Z unit Element electrofission and/or photofission) intermediate materials.Alternately, fusion means are induced as electricity Other known NEUTRON EMISSION process such and structure can also provide neutron (such as, from D-T fusion The 14MeV neutron of reaction), thus in addition to rich in the nuclear fission ignition module of fissionable isotope, Can also be used for this neutron causing propagation fission ripple.
Now been discussed the nucleonics of charging and nuclear fission row ripple, then relevant nuclear fission row will be discussed " nuclear fission ignition " and the further detail below of maintenance of ripple.Appropriateness is rich in picture235U or239Can as Pu The exemplary nuclear fission igniter of centralized positioning of fissioner, containing therefrom removing (as passing through operator Issue an order electrical heating or by taking out one or more control rod) neutron absorber material (as borohydrides etc. Like that), and nuclear fission igniter becomes critical.Local burnup's temperature rises to predetermined temperature, This after image is by reactor cooling system and/or reactivity control system or local thermostat module the most in addition Regulation (was discussing in detail such as Publication about Document: submission on November 28th, 2006, inventor RODERICK A.HYDE, MURIEL Y.ISHIKAWA, NATHAN P.MYHRVOLD and LOWELL L.WOOD, JR., invention entitled " AUTOMATED NUCLEAR POWER REACTOR FOR LONG-TERM OPERATION " U.S. Patent Application No. 12/605,943 Number, hereby it is incorporated by reference into its content).From233U or239The neutron great majority of Pu fast fission are first In local238U or232It is captured on Pu.
It will be understood that by the radial density gradient of fire-resistant moderator as image-stone ink is introduced nuclear fission point Firearm and just around in its fuel region, can be reduced to the enriched uranium of nuclear fission igniter to compare The level that light-water reactor (LWR) fuel is much higher.High moderator-density enables slight enriched fuel to justify Completely burn, reduce moderator-density simultaneously and propagation of effectively fissioning can occur.Therefore, optimal nuclear fission point Firearm design may involve propagation robustness and obtain to from the complete ignition charge district of reactor core with initial criticality Obtain the balance between the short delitescence of quota power availability.Relatively low concentration nuclear fission igniter brings more Breed offspring more, therefore make incubation period longer.
In certain embodiments, the peak value of reactor core assembly reacts in the first of nuclear fission ignition process Stage slowly declines, because while total fissionable isotope storage is continuously increased, but total inventory is spatially More disperse.As selecting initial fuel geometry, the relation of fuel concentration and position and fuel density As a result, it is possible to be arranged to the most just reaching the moment of its minima by maximum reaction.Shortly after that, Maximum reaction start towards it with substantially exceed the fissionable isotope storage being retained in nuclear fission igniter Breeding blanket in the corresponding maximum of fissionable isotope storage rise rapidly.For many situations Speech, director sphere circular casing provides maximum unit power to produce.This moment, can be by reactor core assembly Loading area is referred to as " lighting ".
It is now discussed with being referred to as herein the propagation of the nuclear fission row ripple of " fission fuel burning ".? In aforesaid configuration, the spherical shell that dissipates that maximum unit core power produces continues radially from nuclear fission ignition Device advances to the outer surface of loading area.When reaching outer surface, it generally falls into two spherical zone surfaces, often Individual surface is along axial two rightabout respective propagation of cylinder.At this moment, Ke Nengyi Through developing into the maximum heat power Production capacity of reactor core.This interval is characterized as being two Propagation cores and splits Become the emission period of row ripple burnfront.In certain embodiments, the center in igniting core loading district, because of This generates two contrary propagating waves.This arrangement makes any given time all produce the quality of reactor core of power And double volume, therefore make reactor core peak value unit power generate and halve, thus quantitatively by thermotransport challenge It is reduced to minimum level.But, in other embodiments, as desired by application-specific, one Igniting core loading district on or near end.Such means may cause single propagating wave in some configurations.
The core loading district in further embodiments it is possible to light a fire in multiple places.In other other enforcement In example, as desired by application-specific, core loading of lighting a fire on any 3D position of heap in-core District.In certain embodiments, two can be caused to propagate nuclear fission row ripple, make them deviate from nuclear fission point Ground, fire place is propagated；But, depend on geometry, fission fuel composition, neutron amendment control structure Action or other consideration, can cause and propagate varying number (such as, three or more individual) Nuclear fission row ripple.But, for the ease of understanding that discussion herein refers to without limitation with for purpose of brevity The propagation of two nuclear fission row ripple burnfront.
Arrive from two ripples or opened by their outburst this time forward close to during two opposite end point Begin, nuclear energy generate physics in the reference frame of any one ripple (frame) be all generally effectively the time quiet State.The speed that ripple is advanced by fuel is directly proportional to local neutron flux, and locally neutron flux is the most linear Ground depends on that the collective action of the nuclear fission row ripple neutron budget via centering sub-control system is from reactor The thermal power extracted in core assembly.In a kind of means, as be described in following list of references, Middle sub-control system can utilize thermostat module (not shown) to realize: submit on November 28th, 2006, Inventor RODERICK A.HYDE, MURIEL Y.ISHIKAWA, NATHAN P. MYHRVOLD and LOWELL L.WOOD, JR., invention entitled " CONTROLLABLE LONG TERM OPERATION OF A NUCLEAR REACTOR " U.S. Patent Application No. 11/605, No. 933, hereby it is incorporated by reference into its content.In other means, middle sub-control system can With utilize comprise neutron absorber material and available one or more CRDMs move one or Many control rods realize.
When needing to obtain greater power via the lower temperature coolant flowed in reactor core from reactor, In certain embodiments, reactor core two ends (in certain embodiments, closest with coolant entrance) are made At a temperature of drop to slightly below thermostat module design set-point, thus neutron-absorbing material is from reactor core thermostat module Corresponding son is filled (sub-population) and is recalled, so that local neutron flux increases, and will local hot merit Rate produces to be taken to the level of local material temperature-driven to the set-point of local thermostat module.At some its In its embodiment, can respond the change monitoring temperature, as desired, shim control rod affects Temperature controls.
But, in double burnfront embodiments, this process moves to two in two shuntings of coolant It is less than significant effective to adding hot coolant before individual nuclear burning front.If the temperature of fission fuel Not too high (unrelated with the temperature of the coolant arriving reactor core), then when being not affected by neutron-absorbing material suppression, Two parts in the core loading district that can produce high level core power rise by coolant heating to they The effect of the temperature that the design set-point of module specifies.Then, two coolant streams are by two burning battle arrays Towards two parts of the fuel that burns of center position, therefrom remove remaining nuclear fission and waste heat thermal power, Both in loading area in the heart from loading area out.This arrangement by " reduction " essentially from The multiphonon of crossing of the tailing edge of each front encourages two burnfront to propagate to the two ends of loading area.
It is therefore contemplated that the reactor core neutronics in this configuration is substantially self regulation.Such as, For column reactor core embodiment, as the fuel density-radius product >=200gm/cm of column reactor core2(the most just It is to say, for reasonable fast neutron spectrum, 1-2 of the neutron fission in the reactor core of typical case's composition Mean free path) time, it is believed that reactor core nucleonics is substantially self regulation.So Core Design In a kind of function of neutron reflector can be substantially reduce radiation barrier as it, structural support member, Outermost layer housing and without limitation as control rod (when being equipped with) or thermostat module are (when being equipped with Time) as reactivity control system parts such, the fast neutron fluence that the external component of reactor is seen. Neutron reflector can also carry out shadow by the propagation efficiency in the outermost part of raising fuel and unit power Ring the performance of reactor core.Such impact can improve the economic benefit of reactor.Total energy effect does not uses time low The periphery of loading area, but they have the isotope burning level suitable with the center of loading area.
It can be said that the reactor core neutronics in above-mentioned configuration is substantially self regulation, but other is joined Putting and can run under the control of reactor control system, this reactor control system includes having appropriate electrical The suitable electronic controller on road, and can include as comprising neutron absorber material and may utilize one or many Suitable Mechatronic Systems as one or more control rod that individual CRDM moves.
Finally, if it is desirable, can undesirably inject in coolant stream to enter at any time by neutron inhibitor The irreversible negative of windrow core neutron reaction.Such as, will as desired, may be along with as H2Like that Volatility reduction agent, as BF3Such material slightly loads in coolant stream, can be by occurring in High temperature index therein accelerates otherwise chemical reaction 2BF slowly3+3H2→ 2B+6HF, through anti- Answer heap reactor core coolant hose inwall on substantially homogeneously deposit metal boron.Boron is again highly refractory standard Metal, generally will not migrate from its deposition station.Quantity in reactor core < 100kg(kilogram) the base of boron This uniformly exists, and can not involve negates indefinite extension interval with using actuating unit near reactor Reactor core neutron reaction.
It is, in general, that it is appreciated by those skilled in the art that can pass through varied hardware, Software, firmware and/or their any assembly are individually and/or the various aspects described herein that realizes of collective Can regard as being made up of various types of " circuit ".Therefore, as used throughout, " circuit " include but It is not limited to the circuit containing at least one discrete circuit, circuit containing at least one integrated circuit, contains Universal computing device (the example that the circuit of at least one special IC, formation are configured by computer program As, the general-purpose computations being made up of the computer program at least partly realizing process as herein described and/or equipment Machine or the micro-process being made up of the computer program at least partly realizing process as herein described and/or equipment Device) circuit, form storage device (such as, various forms (such as, random access memory, flash, only Read etc.) memorizer) circuit and/or formed communication equipment (such as, modem, communication hand over Change planes, opto-electronic conversion equipment etc.) circuit.It is appreciated by those skilled in the art that herein Described theme can in the way of analog or digital or combinations thereof realize.
It is, in general, that it is appreciated by those skilled in the art that various embodiments described herein Can by various types of Mechatronic Systems, individually and/or collective realizes, this Mechatronic Systems contain as hardware, Varied electricity parts as software, firmware and/or their substantially any assembly；And as just Body, elasticity or torsion body, hydraulic system, Electromagnetically actuated equipment and/or their substantially any assembly Like that, varied parts of mechanical force or motion can be transmitted.Therefore, as used throughout, " dynamo-electric System " include but not limited to operationally with transducer (such as, actuator, motor, piezoquartz, MEMS (MEMS) etc.) couple circuit, circuit containing at least one discrete circuit, contain There are the circuit of at least one integrated circuit, circuit containing at least one special IC, formed by counting The universal computing device that calculation machine program is constituted is (by least partly realizing process as herein described and/or equipment Computer program constitute general purpose computer or by least partly realizing process as herein described and/or equipment Computer program constitute microprocessor) circuit, formed storage device (such as, various forms (example Such as, random access memory, flash, read-only etc.) memorizer) circuit, form communication equipment (such as, Modem, communication switchboard, opto-electronic conversion equipment etc.) circuit and/or as light or other be similar to Any non-electrical analog as thing.Those of ordinary skill in the art it will also be understood that, the example of electric system Son includes but not limited to consumer electronics system miscellaneous, armarium, and as motorized transport system System, factory automation system, security system and/or the communication/system that calculates other system such.Ability The those of ordinary skill in territory is it should be appreciated that as used herein Mechatronic Systems is not necessarily limited to have electricity Activate and both system mechanically actuated, unless otherwise indicated by context.
Exemplary embodiments
Since having been presented for the initiation about nuclear fission row ripple and the general introduction of propagation, now by unrestricted Property example explanation exemplary embodiments.
It is hereafter to describe these a series of flow charts realized.In order to make it easy to understand, by these flow chart groups Being made into initial flowchart and show the realization via exemplary realization, hereafter, flow chart then shows conduct Set up at the beginning of one or more relatively early show on flow chart, sub-unit operations or optional feature operation The alternate embodiments of beginning flow chart and/or expansion.Those of ordinary skill in the art is it will be understood that make herein Displaying style (such as, from show exemplary realization flow chart displaying from the beginning of, hereafter follow-up Flow chart provides additional detail and/or further detail below) it is usually for the ease of people rapidly and easily Understand that various process realizes.Additionally, those of ordinary skill in the art should will further appreciate that, make herein Displaying style also adapt with modularity and/or Object-oriented Programming Design normal form.
Referring now to Figure 1A and by general introduction for, exemplary methods 10 be for operation nuclear fission row ripple Reactor and provide.Further referring to Figure 1B, citing ground rather than restrictively show nuclear fission row The parts of the exemplary nuclear fission row ripple reactor core 12 of ripple reactor.Fission fuel subassembly 14 It is accommodated in reactor core assembly 16.In order to contribute to clear for the sake of, Figure 1B may exemplified with The part of all fission fuel subassemblies 14 that can accommodate in the embodiment of reactor core assembly 16.
Reference frame (reference of frame) is defined in reactor core assembly 16.In some embodiments In, reference frame can be defined by x dimension, y-dimension and z-dimension.In some other embodiments, Reference frame can be defined by radial dimension and axial dimension.In some other embodiments, reference frame Axial dimension and transverse dimensions can be included.
In certain embodiments, fission fuel subassembly 14 can be as fission fuel rod, plate, ball Deng such individually fission fuel element.In some other embodiments, fission fuel subassembly 14 Can be fission fuel assemblies it is to say, be grouped into two or more independent cores of an assembly Fission fuel element.Unrelated with the embodiment of fission fuel subassembly 14, it is included in fission fuel Fission fuel in subassembly 14 can be the fission fuel of any suitable type as above.
For general introduction, method 10 is from the beginning of frame 18.In frame 20, anti-at nuclear fission row ripple In answering the fission fuel subassembly 14 in the reactor core assembly 16 of heap reactor core 12, make nuclear fission row Ripple burnfront 22 propagates (such as arrow 24 indication) along the first and second dimensions.In frame 26, with The shape along the second dimension restriction nuclear fission row ripple burnfront 22 is retrained according to the dimension of selected group Mode, along the first dimension from respective primary importance to the controlled migration fission fuel in respective second position ground Subassembly 14 selected several.The method 10 is terminated in frame 28.
Now by non-limitative example, exemplary details is described.
Fission fuel subassembly 14 and the dimension Existential Space relation being designated as the first and second dimensions.Example As, in certain embodiments, fission fuel subassembly 14 can be along the second dimension elongation.At some In embodiment, the second dimension can be y-dimension or axial dimension.In some other embodiments, second Dimension can be x dimension, y-dimension or transverse dimensions.
Additionally, in certain embodiments, the first dimension can almost with the stretching of fission fuel subassembly 14 Major axis is orthogonal.In certain embodiments, the first dimension and the second dimension can be the most mutually orthogonal.
Various dimensions can be designated as the first dimension and the second dimension.Such as, in certain embodiments, First dimension can include radial dimension, and the second dimension can include axial dimension.At some, other is real Executing in example, the first dimension can include axial dimension, and the second dimension can include radial dimension.One In a little embodiments, the first dimension can include axial dimension, and the second dimension can include transverse dimensions. In some other embodiments, the first dimension can include transverse dimensions, and the second dimension can include axle To dimension.Configuring as typical commercial light-water reactor, the column reactor core that assembly axially extends In, the first dimension can be radial dimension, and the second dimension can be axial dimension.As CANDU In the configuration of heavy water reactor other reactor such configuration, fuel assembly can be stretched along the first dimension Long, and can move along laterally or radially the second dimension.
As illustrated in Figure 1B, according to each attribute, the position in reactor core 12 can be characterized into One position and the second position.It is, in general, that a position may be considered that and is around fission fuel packet One space of one areas adjacent of the reactor core 12 of part 14.One position typically can also be by It is considered just around a space of any given area in reactor core 12, or may be considered that It it is most of region of reactor core 12.Such as, and referring additionally to Fig. 1 C, in some embodiments In, primary importance can include outer position 30, and the second position can include inner position 32.Such as figure Illustrated in 1C, in certain embodiments, inner position 32 and outer position 30 can based on reactor The geometry proximity of the core of reactor core 12.In some other embodiments, inner position and position, outside Putting can be based on neutron flux so that the neutron flux on inner position is led to more than the neutron on outer position Amount.In some other embodiments, inner position and outer position can be based on reactivities so that the inside K on positioneffectiveMore than the k on outer positioneffective.The embodiment representing row ripple reactor can have There is an outside being included in propagating wave, or the outer position of position in the direction along propagating wave, and position, the inside Put the position that can include that nuclear fission row ripple is passing through or passing through.
Be given by further example and referring additionally to Fig. 1 D, in certain embodiments, primary importance Can include that inner position 32 and the second position can include outer position 30.As illustrated in Fig. 1 D, In some embodiments, inner position 32 and outer position 30 can be based on the centers with reactor core 12 The geometry proximity of part.In some other embodiments, inner position and outer position can based in Sub-flux so that the neutron flux on inner position is more than the neutron flux on outer position.At some its In its embodiment, inner position and outer position can be based on reactivities so that the k on inner positioneffective More than the k on inner positioneffective.In other embodiments, can be with accounting in those regions occurs Leading nuclear reaction inwardly describes and outer position.Being given by nonrestrictive example, inner position can To characterize by accounting for leading nuclear fission reaction, and outer position can be by accounting for master on fertile material Lead core absorption reaction to characterize.
Characterize into inner position with by primary importance and the second position or outer position be unrelated, primary importance and The second position can characterize according to other attribute.Such as, in certain embodiments, primary importance and Two positions can be on the opposite side of reference value along the first dimension.In some other embodiments, the One position and the second position can include at least one attribute substantially equalized.Such as, substantially equalize to A few attribute can include the geometry proximity of core with reactor core, neutron flux, anti- Ying Xing etc..
Be given by nonrestrictive example and with reference to Fig. 1 E, can retrain with the dimension according to selected group Axially confine the mode of the shape of nuclear fission row ripple burnfront 22, from respective inner position 32 to each Outer position 30 the most controlled migration fission fuel subassembly (for clarity, not shown) Selected several.Be given without limitation by illustration, it is shown that the shape of nuclear fission row ripple burnfront 22 Shape is with the Axial changes of the radial motion of fission fuel subassembly (not shown).Left figure splits exemplified with core Become the original shape of row ripple burnfront 22, it will be understood that for clarity, merely illustrate nuclear fission row / 4th girths of ripple burnfront 22.
In middle figure, after selected fission fuel subassembly (not shown) has burnt the desired time Or according to desired reactivity parameter (without limitation as burnup), by selected fission fuel Subassembly (not shown) position 32 radial migration from the inside is to outer position 30.Reactivity is from footpath It is moved radially outward to outer position 30(such as to the peak position (as shown in the left diagram) being on inner position 32 Shown in middle figure).
Within the life-span of nuclear fission row ripple reactor core 12, outer position can be arrived in position 32 from the inside 30 radially outward migrate other fission fuel subassembly (not shown).As the most additionally to moving outside It is that move as a result, it is possible to the nuclear fission prevented in nuclear fission row ripple reactor core 12 on radially internal position is fired Material subassembly (not shown), burn to obtain ratio in radially external position in nuclear fission row ripple reactor core 12 Fission fuel subassembly (not shown) many.As shown at right, the most radially outward move Moved sufficient amount of fission fuel subassembly, then the shape of nuclear fission row ripple burnfront 22 can be near It is similar to Bezier (Bessel) function.Additionally, the most radially outward migrated sufficient amount of Fission fuel subassembly, then all or almost all nuclear fission in nuclear fission row ripple reactor core 12 Fuel subassembly can reach or at substantially the same time close to the burnup limit of each of which.In such situation Under, can farthest use fission fuel subassembly in nuclear fission row ripple reactor core 12.
Be given by another non-limitative example and with reference to Fig. 1 F, can be with according to the dimension of selected group Constraint axially confines the mode of shape of nuclear fission row ripple burnfront 22, from respective inner position 32 to Each selected several 14 of outer position 30 the most controlled migration fission fuel subassembly, and And divide to respective inner position 32 the most controlled migration fission fuel from respective outer position 30 Selected by other of assembly several 14 '.It is to say, inside exchange between position 32 and outer position 30 Selected fission fuel subassembly 14 and 14 '.
Be given without limitation by illustration, it is shown that the shape of nuclear fission row ripple burnfront 22 is split with core Become the Axial changes so exchanging radial motion of fuel subassembly 14 and 14 '.Left figure is exemplified with nuclear fission The original shape of row ripple burnfront 22.In left figure, fission fuel subassembly 14 is containing splitting than core Become the fissible inclusions of fuel subassembly more than 14 '.Such as, fission fuel subassembly 14 is probably core The part of the ignition module of fission row ripple reactor core 12.For another example, fission fuel Subassembly 14 potentially includes as absorbing fast spectrum neutron in nuclear fission row ripple reactor core 12 subsequently Transmuting becomes the result of fertile isotope, the fissile material of regeneration from fertile isotope material. On the contrary, fission fuel subassembly 14 ' is containing the fissible inclusions fewer than fission fuel subassembly 14. In some cases, fission fuel subassembly 14 ' can include than fission fuel subassembly more than 14 Fertile isotope inclusions.In this case, fission fuel subassembly 14 ' can compare nuclear fission Fuel subassembly 14 more absorbs composes neutron soon.
In right figure, selected fission fuel subassembly 14 position 32 from the inside is radially outward moved Move on to outer position 30, and by selected fission fuel subassembly 14 ' position 30 from the outside radially-inwardly Move to inner position 32.At mutual fission fuel subassembly 14 and 14 ' afterwards, nuclear fission row is made Before the axial distribution of ripple burnfront 22 and so exchange, nuclear fission row ripple burnfront 22 axially divides Cloth (ginseng seeing left image) compare more compact evenly.As a result of which it is, in certain embodiments, can be core Fission row ripple burnfront 22 realizes generally uniform distribution or is uniformly distributed.In some other embodiments, May not want that and realize generally uniform distribution for nuclear fission row ripple burnfront 22 or be uniformly distributed.So In the case of, may only want to reorientate fissile material or reorientate fertile isotope material. In some other embodiments, it may be desirable to along radial dimension expansion nuclear fission row ripple burnfront 22.
Referring additionally to Fig. 1 G, it is also possible to by as migrated along radial dimension above with reference to Fig. 1 F discussion Fission fuel subassembly 14 and 14 ', limits the shape of nuclear fission row ripple burnfront 22 in radial dimension. The radial distribution of nuclear fission row ripple burnfront 22 may be considered that and represents neutron leakage neutron current.Fig. 1 G Left figure and the right view illustrating the axially dimension corresponding respectively to the left figure of Fig. 1 F and right figure.
Referring now to Fig. 1 H, can be to retrain the burning of radially defined nuclear fission row ripple according to the dimension of selected group The mode of the shape of front 22, splits to the respective second position the most controlled migration core from respective primary importance Become the selected several of fuel subassembly 14.
The original shape of the nuclear fission row ripple burnfront 22 that left figure is watched exemplified with axially dimension, institute Fission fuel subassembly 14 is selected to be in the first position z, r, φOn 1.Shown in the purpose in order to illustrate In example, fission fuel subassembly 14 is at primary importance z, r, φ1On contribute to for a certain reason, May be confirmed as exceeding in primary importance z, r, φ1The reaction of upper desired response magnitude.Such as, core Fission fuel subassembly 14 is probably the part of the ignition module of nuclear fission row ripple reactor core 12.Lift For another example, fission fuel subassembly 14 potentially includes as at nuclear fission row ripple reactor Core 12 absorbs the neutron transmuting subsequently of fast spectrum and becomes the result of fertile isotope, from convertible coordination The fissile material of regeneration in cellulosic material.As a result of which it is, nuclear fission row ripple burnfront 22 may be too much Along primary importance z, r, φ1Radial propagation.
As shown at right, selected fission fuel subassembly 14 along transverse dimensions φ from primary importance Z, r, φ1Lateral transfer is to second position z, r, φ2.It will be understood that as selected fission fuel subassembly 14 from primary importance z, r, φ1Lateral transfer is to second position z, r, φ2Result, the most radially defined The shape of nuclear fission row ripple burnfront 22.Selected fission fuel subassembly 14 from primary importance z, R, φ1Lateral transfer is to second position z, r, φ2From primary importance z, r, φ1Remove fissible inclusions, And fissible inclusions is added second position z, r, φ2In.As shown at right, nuclear fission row ripple burning The shape of front 22 is at primary importance z, r, φ1Near shorten along radial dimension r, and at second Put z, r, φ2Neighbouring elongated along radial dimension r.
Frame 26 splits to the respective second position, controlled migration core along the first dimension from respective primary importance Become the selected several of fuel subassembly 14 and may need one or more processes.Such as, and referring additionally to Fig. 1 I and 1J, in certain embodiments, in frame 26 along the first dimension from respective primary importance to respectively From several selected by the controlled migration fission fuel subassembly 14 in second position ground, can include such as arrow 36 indications (Fig. 1 J), rotate selected by fission fuel subassembly 14 several at least one in frame 34 Individual.It will be understood that as desired, rotate selected by fission fuel subassembly 14 several in frame 34 At least one, it is possible to use any suitable reactor core fuel management system is carried out.Further it may be desired to rotation Turn selected fission fuel subassembly 14, in order to farthest reduce or prevent as fission fuel is grouped The deformation bending such reactor structural material of part.
For for another example and referring additionally to Fig. 1 K and 1L, in some other embodiments, Frame 26 fires to the controlled migration nuclear fission in respective second position ground along the first dimension from respective primary importance Material the selected several of subassembly 14 can include such as arrow 40 indication (Fig. 1 L), reverse core in frame 38 Selected several at least one of fission fuel subassembly 14.It will be understood that as desired, in frame 38 Selected several at least one of reverse fission fuel subassembly 14 can utilize any suitable heap in-core Fuel management system is carried out.Reverse fission fuel subassembly 14 can cause fission fuel subassembly The entrance (before Dian Dao) of 14 becomes the outlet (after Dian Dao) of fission fuel subassembly 14, otherwise As the same.Such overturning can cause dividing fission fuel on the end of fission fuel subassembly 14 The axially uniform thermal stress of assembly 14 and/or radiation effect.Any such radiation effect is all probably temperature That degree is correlated with and/or relevant with the change of the neutron flux on the axle head of fission-type reactor reactor core 12.Will Understand, the two ends of the reverse fission fuel subassembly 14 causing overturning of fission fuel subassembly 14 The second position is moved to from primary importance around reverse central point.But, in some cases it is also possible to Wish laterally to change the position of assembly.
It will also be understood that, any one or more dimensions can be selected to retrain for application-specific as desired.Example As, in certain embodiments, the dimension constraint of selected group can include the predetermined maximum along the second dimension Distance.
In some other embodiments, the dimension constraint of selected group can be at least one burnfront criterion Function.Such as, burnfront criterion can include neutron flux.Some arrange in, can by Sub-flux is associated with selected several at least one of fission fuel subassembly 14.At some, other is real Executing in example, burnfront criterion can include neutron fluence (fluence).In some arrange, can be by Neutron fluence is associated with selected several at least one of fission fuel subassembly 14.
In some other embodiments, burnfront criterion can include burnup.In some arrange, can So that several at least one selected by burnup and fission fuel subassembly 14 is associated.In such peace In row, it may be desirable to by several from having the first of the first burn-up rate selected by fission fuel subassembly 14 Position moves to the second position with the second burn-up rate.If selected fission fuel subassembly 14 will Terminate its service life, then primary importance can be the position characterized by high burnup rate, and the second position Can be by the burn-up rate reducing burn-up rate (the high burnup rate relative in primary importance) or almost null value The position characterized.In the embodiment that fission fuel subassembly 14 is being bred, it may be desirable to core is split Become fuel subassembly 14 and move to have high burnup rate (relative to the from the primary importance with low burn-up rate The burn-up rate of one position) the second position.
In some other embodiments, burnfront criterion can include the institute of fission fuel subassembly 14 Select the burnfront position that several at least one is interior.Burnfront position can be anti-by nuclear fission row ripple The feature in heap reactor core 12 or fission fuel subassembly 14 is answered to characterize.Such feature can include But it is not limited to fission rate, the rate of increase, power output, temperature, reactivity etc..
It will be understood that it is controlled to respective second position ground from respective primary importance along the first dimension in frame 26 Migrate the selected several of fission fuel subassembly 14, can enter in any mode desired by application-specific OK.Such as, and additionally Parameter Map 1M(and such as Fig. 1 C and 1D indication), in certain embodiments, In frame 26 along the first dimension from respective primary importance to the controlled migration nuclear fission in ground of the respective second position Fuel subassembly 14 selected several, can be included in frame 42 along the first dimension from respective first Put to several selected by the respective second position the most controlled migration fission fuel subassembly 14.To understand , as desired, the radial migration in frame 42 can utilize any suitable reactor core fuel management system to enter OK.
In some other embodiments, and referring additionally to Fig. 1 N and 1O, along the first dimension in frame 26 Spend from respective primary importance to selected by the controlled migration fission fuel subassembly 14 in respective second position ground Several can include such as arrow 46 indication, in frame 44 along the first dimension from respective primary importance to respectively From several selected by the second position the most controlled migration fission fuel subassembly 14.It will be understood that as scheduled Hoping, the spiral in frame 44 migrates and any suitable reactor core fuel management system can be utilized to carry out.
In some other embodiments, and referring additionally to Fig. 1 P and 1Q, along the first dimension in frame 26 Spend from respective primary importance to selected by the controlled migration fission fuel subassembly 14 in respective second position ground Several can include such as arrow 50 indication, in frame 48 along the first dimension from respective primary importance to respectively From several selected by the second position the most controlled migration fission fuel subassembly 14.It will be understood that as scheduled Hoping, the axial migration in frame 48 can utilize any suitable reactor core fuel management system to carry out.
It will be understood that the shape of nuclear fission row ripple burnfront 22 can be by leading to as neutron without limitation Amount, neutron fluence, burnup and/or reactivity (or their any composition) are such, with nuclear fission row Any parameter that ripple burnfront 22 is associated limits.It will also be understood that, nuclear fission row ripple burnfront 22 can have any shape as desired by application-specific.Such as, and referring additionally to Fig. 1 R, one In a little embodiments, the shape of nuclear fission row ripple burnfront 22 can be approximately spherical.At some other In embodiment and referring additionally to Fig. 1 S, the shape of nuclear fission row ripple burnfront 22 can connect with selected Continuous curved surface is substantially consistent.In certain embodiments and referring additionally to Fig. 1 T, nuclear fission row ripple burns It is the most rotational symmetric that the shape of front 22 may be about the first dimension.In some other embodiments with And referring additionally to Fig. 1 U and 1V, the shape of nuclear fission row ripple burnfront 22 can have around the second dimension The substantially n fold rotational symmetry of degree.
Those of ordinary skill in the art knows, strides across reactor core and keeps substantially constant, " smooth " combustion Burn distribution (as Bessel function) farthest reduce heap in-core fission fuel subassembly it Between power peak, and improve the utilization rate of fuel.It is expert in ripple fission-type reactor, as it has been described above, The size of the combustion zone of reactor trends towards because of high-conversion rate expanding.Combustion zone keeps as convertible coordination Sufficient feed-in nuclear material as cellulosic material or fissile material, in order to keep high-conversion rate.
It will be understood that in some reactors configure, exist migrate as mentioned above fission fuel subassembly with Just the advantage keeping desired reactor burnfront feature.Such as, by fission fuel subassembly radially Move to combustion zone can be risen the work of reaction zone fertile isotope material or fissile material supplied With.It is moved radially outward fission fuel subassembly to may be used for splitting the core having arrived at its burnup limit Become fuel subassembly to move to beyond the region of high neutron activity.It is moved radially outward and can be used for passing through Non-burning region reduces before making fissible, incendivity fissionable fuel be diffused into the power of combustion zone Density.It will be understood that combine, by moving radially to move with spiral, the further shaping allowed as burnfront The increase of finer spiral moves moving radially of combination with orientation.It will also be understood that, in some cases, Can be by fission fuel subassembly and the fission fuel subassembly exchange (or exchange) on other position. In this case, can by from convertible blanket district fertile isotope material with carry out autothermal reactor The material of grilling thoroughly of combustion zone exchanges, and in other cases, can exchange from direct neighbor reactor core The fission fuel of position, in order to two or more fission fuel subassembly exchange positions.
In certain embodiments and referring additionally to Fig. 1 W, nuclear fission row ripple burnfront 22 is along second The shape of dimension can be asymmetrical.In some arrange, the shape of nuclear fission row ripple burnfront 22 Can rotate asymmetric around the second dimension.
In certain embodiments and referring additionally to Fig. 1 X, method 20 is additionally may included in frame 52 utilization Nuclear fission row ripple ignition module (not shown) initiated core fission row ripple burnfront 22.Utilize nuclear fission row Ripple ignition module initiated core fission row ripple burnfront il-lustrative example have already discussed above, here without Repeat.Referring additionally to Fig. 1 Y, in frame 54 can along the first dimension from respective primary importance to respectively Nuclear fission row wave point fire was removed before several selected by the second position controlled migration fission fuel subassembly At least one of assembly.Referring additionally to Fig. 1 Z, in certain embodiments, along first in frame 54 Dimension from respective primary importance to several selected by the respective second position controlled migration fission fuel subassembly Before, at least one removing nuclear fission row ripple ignition module may include that in frame 56 along first Dimension from respective primary importance to several selected by the respective second position controlled migration fission fuel subassembly Before, from the second position, remove at least one of nuclear fission row ripple ignition module.
In certain embodiments and referring additionally to Figure 1A A, in block 58, along the first dimension from respectively From primary importance before several selected by the respective second position controlled migration fission fuel subassembly, make Nuclear fission row ripple reactor becomes subcritical.Such as, and referring additionally to Figure 1A B, in some embodiments In, make nuclear fission row ripple reactor become in block 58 and in block 60 neutron is inhaled subcritical can including Receive in material insertion reaction heap reactor core.
Referring additionally to Figure 1A C, in certain embodiments, in frame 62 can along the first dimension from respectively From primary importance after several selected by the respective second position controlled migration fission fuel subassembly, weight Newly set up critical.Such as, and referring additionally to Figure 1A D, in certain embodiments, in frame 62 again Set up and critical can include removing from reactor core in block 64 at least part of of neutron absorber material.
In certain embodiments and referring additionally to Figure 1A E, in frame 66, can be along the first dimension From respective primary importance to selected by the respective second position controlled migration fission fuel subassembly several it Before, close nuclear fission row ripple reactor.Referring additionally to Figure 1A F, in frame 68, can be along first Dimension from respective primary importance to several selected by the respective second position controlled migration fission fuel subassembly Afterwards, nuclear fission row ripple reactor is restarted.
Referring now to Fig. 2 A and 1B, exemplary methods 200 is for controlling nuclear fission row ripple burnfront 22 There is provided along the nuclear fission row ripple reactor of the first and second dimensions propagation.Method 200 is from frame 202 Start.In frame 204, in fission fuel subassembly 14, according to selected group dimension retrain along Second dimension determines the desired shape of nuclear fission row ripple burnfront 22.In block 206, to respond The mode of desirable shape, determine fission fuel subassembly 14 selected several along the first dimension from each Primary importance is to the migration of the respective second position.
Referring additionally to Fig. 2 B, in certain embodiments, in block 210, nuclear fission row ripple burning battle array is determined The existing shape in face 22.It will be understood that as desired, determine nuclear fission row ripple burnfront in block 210 The existing shape of 22, can be with the desired shape determining nuclear fission row ripple burnfront 22 in frame 204 Shape is carried out relatively.In certain embodiments, nuclear fission row ripple burnfront 22 is determined in block 210 Existing shape, can be before determining the desired shape of nuclear fission row ripple burnfront 22 in frame 204 Carry out.In some other embodiments, determine the existing of nuclear fission row ripple burnfront 22 in block 210 Shape, can with in frame 204, determine that the desired shape of nuclear fission row ripple burnfront 22 is almost simultaneously Carry out.In some other embodiments, determine the existing of nuclear fission row ripple burnfront 22 in block 210 Shape, can be carried out after determining the desired shape of nuclear fission row ripple burnfront 22 in frame 204. As desired, can include determining that fission rate, estimate burnup, the rate of increase, Temperature Distribution, power distribution, Determine to the reactivity worth of the fission fuel of having moved in assembly operating history and each position and wished Hope shape.
It will be understood that can be desired shape and/or the holding as setting up nuclear fission row ripple burnfront 22 The desired shape of nuclear fission row ripple burnfront 22 is such, and any purpose desired by application-specific migrates Fission fuel subassembly 14 selected several.Such as, in certain embodiments and referring additionally to figure 2C, in block 206 in the way of the desired shape of response, determines the selected of fission fuel subassembly 14 Several along the first dimension from respective primary importance to the migration of the respective second position, frame 212 can be included in In in the way of setting up desired shape, determine the selected several along first of fission fuel subassembly 14 Dimension from respective primary importance to the migration of the respective second position.In some other embodiments and additionally With reference to Fig. 2 D, in block 206 in the way of the desired shape of response, determine fission fuel subassembly 14 selected several along the first dimension from respective primary importance to the migration of the respective second position, can wrap Include in block 214 in the way of keeping desired shape, determine the selected several of fission fuel subassembly 14 Individual along the first dimension from respective primary importance to the migration of the respective second position.
It will be understood that inter alia, it is also possible to it is desired to determine carrying out the time of desired migration.To this end, And with reference to Fig. 2 E, in certain embodiments, in block 216 in the way of the desired shape of response, really Determine to migrate fission fuel subassembly 14 from respective primary importance to the respective second position along the first dimension Selected several time.It will also be understood that, as desired, can be on any point performing method 200 Make the determination in frame 216.
In certain embodiments, the selected several of fission fuel subassembly 14 can be migrated.Referring additionally to Fig. 2 F, in block 218 can be in the way of the desired shape of response, along the first dimension from respective first Position migrates selected by fission fuel subassembly 14 several to the respective second position.
It will be understood that some aspects of frame 200 are similar to some aspects of the method 10 of mistake described above.This A little similar aspects will be mentioned, but for simplicity, it is not necessary to their details is described to understand.
Such as, and referring additionally to Figure 1B, in certain embodiments, fission fuel subassembly 14 can With along the second dimension elongation.First dimension can almost with the axis of elongation of fission fuel subassembly 14 just Hand over.First dimension and the second dimension can be the most mutually orthogonal.
In further example and additionally referring still to Figure 1B, the first dimension can include radially tieing up Degree, and the second dimension can include axial dimension.In some other embodiments, the first dimension can be wrapped Include axial dimension, and the second dimension can include radial dimension.Any kind of fission-type reactor all may be used To include the fission fuel subassembly extending through whole axial dimension, and multiple fission fuel subassembly Extend through radial dimension.Nuclear fission row ripple can be to depend on, in this case, depends on nuclear fission row Ripple power from interior zone to perimeter is distributed and dissipates, and is different from the speed edge along radial dimension Axially dimension to propagate, especially in column reactor core configures.May want in this case into The radial migration of row fission fuel subassembly, in order to protect waveform and the feature of axially dimension.Example As, the axial range making nuclear fission row ripple travel to reactor region will promote that neutron is at reactor core Leak out from reactor core on axle head.As it has been described above, such leakage reduces in fission-type reactor Can be switched to fissible conversion.Burnfront can be moved radially and expand into unwished-for axial location Fission fuel subassembly, in order to fission fuel subassembly by fission fuel subassembly, reduce or Limit the neutron activity domination that burnfront propagates further on the place in unwished-for place.At other In the case of, it may be desirable to propagate according to the nuclear fission row ripple of axially dimension and move radially fission fuel Subassembly, in order to can be by the fissible material in the axial region having regenerated fission fuel subassembly Material is used in the other parts of fission-type reactor reactor core.On given axial location, can be by controlled Migrating fission fuel subassembly makes burnfront be heterogeneous along radial dimension, in order to as desired, Concentration alternate district can be set up.Highly enriched district places by dilution or low enrichment region and makes highly enriched district let out The neutron draining to low enrichment region increases, thus contributes to fertile isotope material is converted into fissible material Material.It will be understood that above-mentioned migration can promote to limit along the second dimension along the propagation of the first dimension Propagate ground to carry out.
In some further examples and additionally referring still to Figure 1B, the first dimension can include axially tieing up Degree, and the second dimension can include transverse dimensions.In other example, the first dimension can include laterally Dimension, and the second dimension can include axial dimension.
As discussed above and referring additionally to Fig. 1 C, primary importance can include outer position 30, and Two positions can include inner position 32.The most as discussed above, inner position 32 and outer position 30 can be based on the geometry proximity with the core of reactor core 12.Inner position 32 and outside Position 30 can be based on neutron flux so that the neutron flux on inner position 32 is more than outer position 30 On neutron flux.As discussed above, inner position 32 and outer position 30 can based on reactivity, Make the k on inner position 32effectiveMore than the k on outer position 30effective。
In certain embodiments and referring additionally to Fig. 1 D, primary importance can include inner position 32, Outer position 30 can be included with the second position.Inner position and outer position can based on reactor The geometry proximity of the core of core 12, and/or based on neutron flux so that on inner position Sub-flux is more than the neutron flux on outer position, and/or based on reactivity so that on inner position keffectiveMore than the k on outer positioneffective。
In certain embodiments and as shown in Figure 1B, primary importance and the second position can be along the first dimensions Degree is on the opposite side of reference value.
The most as shown in Figure 1B, in certain embodiments, primary importance and the second position can include substantially At least one attribute of equilibrium.Such as, at least one attribute can include and the center of reactor core 12 Geometry proximity, neutron flux and/or the reactivity of part.
In certain embodiments and referring additionally to Fig. 2 G, in block 206, determine that fission fuel is grouped Part 14 selected several along the first dimension from respective primary importance to the migration of the respective second position, permissible It is included in frame 220, determines selected several rotation of at least one of fission fuel subassembly 14. In certain embodiments and referring additionally to Fig. 2 H, in block 206, determine fission fuel subassembly 14 selected several along the first dimension from respective primary importance to the migration of the respective second position, can wrap Include in frame 222, determine selected several at least one reverse of fission fuel subassembly 14.
In certain embodiments, the dimension constraint of selected group can include the predetermined maximum along the second dimension Distance.In some other embodiments, the dimension constraint of selected group can be that at least one burnfront is accurate Function then.Such as, burnfront criterion can include nonrestrictive, as being grouped with fission fuel Neutron flux as at least one selected several neutron flux being associated of part 14.As another Example, burnfront criterion can include nonrestrictive, as with fission fuel subassembly 14 selected by Neutron fluence as the neutron fluence that several at least one is associated.As another example, burning Front criterion can include nonrestrictive, as with fission fuel subassembly 14 selected by several at least Burnup as one burnup being associated.In some other embodiments, burnfront criterion can be wrapped Include at least one selected several interior burnfront position of fission fuel subassembly 14.
Referring additionally to Fig. 2 I, in certain embodiments, in block 206, fission fuel subassembly is determined 14 selected several along the first dimension from respective primary importance to the migration of the respective second position, can wrap Include in frame 224, determine fission fuel subassembly 14 selected several along the first dimension from respective One position is to the radial migration of the respective second position.In certain embodiments and referring additionally to Fig. 2 J, In frame 206, determine fission fuel subassembly 14 selected several along the first dimension from respective first Put the migration to the respective second position, can be included in frame 226, determine fission fuel subassembly 14 Selected several along the first dimension from respective primary importance to the spiral of the respective second position migrate.One In a little other embodiments and referring additionally to Fig. 2 K, in block 206, determine fission fuel subassembly 14 selected several along the first dimension from respective primary importance to the migration of the respective second position, can wrap Include in frame 228, determine selected several axial translation of fission fuel subassembly 14.
Referring additionally to Fig. 2 L, in certain embodiments, in frame 204, determine nuclear fission row ripple burnfront The desired shape of 22, can be included in frame 230 and determine nuclear fission row ripple burnfront 22 substantially Spherical.In some other embodiments and referring additionally to Fig. 2 M, true along the second dimension in frame 204 Determine the desired shape of nuclear fission row ripple burnfront 22, can be included in frame 232 and determine nuclear fission row The continuous bend surface configuration of ripple burnfront 22.In some other embodiments, curved surface can be made Expand the surface area of burnfront.In such embodiments, combustion zone is made to leak into the neutron of breeding blanket Increase.
The desired shape of nuclear fission row ripple burnfront 22 can be any shape.As discussed above, In various embodiments, the desired shape of nuclear fission row ripple burnfront 22 may be about the second dimension The most rotational symmetric；The desired shape of nuclear fission row ripple burnfront 22 can have around the second dimension The substantially n fold rotational symmetry of degree；The desired shape of nuclear fission row ripple burnfront 22 can be with right and wrong pair Claim；And/or the desired shape of nuclear fission row ripple burnfront 22 may be about the second dimension and rotates Asymmetric.In some other embodiments, symmetric shape symmetrical for n weight can be transformed into nuclear fission The discrete combustion zone of row ripple reactor in-core.Can be further for example, it is possible to burnfront is transformed into Travel to the ripple of n or less discrete (it is to say, neutron decoupling) combustion zone (seeing Fig. 1 V) Lobe.
Some embodiments can illustratively provide by sexual system.Such as, and referring now to Fig. 3 A, example Exemplary system 300 is for determining the migration of fission fuel subassembly (being not shown in Fig. 3 A) and to carry Confession.Being given by nonrestrictive example, system 300 can provide execution method 200(Fig. 2 A-2M) Suitable system environments.In certain embodiments and referring additionally to Figure 1B, for along first and second The nuclear fission row ripple burnfront 22 that dimension is propagated, is configured to circuit 302 at fission fuel subassembly In 14, the dimension according to selected group retrains, determines nuclear fission row ripple burnfront 22 along the second dimension Desired shape.It is configured to circuit 304, in the way of the desired shape of response, determine fission fuel Subassembly 14 selected several along the first dimension from respective primary importance to the migration of the respective second position.
It is, in general, that it is appreciated by those skilled in the art that can pass through varied hardware, Software, firmware and/or their any assembly are individually and/or the various aspects described herein that realizes of collective Can regard as being made up of various types of " circuit ".Therefore, as used throughout, " circuit " include but It is not limited to the circuit containing at least one discrete circuit, circuit containing at least one integrated circuit, contains The circuit of at least one special IC, formed be made up of computer program universal computing device (by At least partly realize process as herein described and/or equipment computer program constitute general purpose computer or The microprocessor being made up of the computer program at least partly realizing process as herein described and/or equipment) Circuit, form storage device (such as, various forms (such as, random access memory, flash, read-only etc.) Memorizer) circuit and/or formed communication equipment (such as, modem, communication switchboard, Opto-electronic conversion equipment etc.) circuit.It is appreciated by those skilled in the art that as herein described Theme can in the way of analog or digital or combinations thereof realize.
Referring additionally to Fig. 3 B, in il-lustrative example, circuit 302 and/or circuit 304 can be embodied Calculating system 306(is become to be referred to as master computer or system).In exemplary embodiments, by central authorities Processing unit (" CPU ") (or microprocessor) 308 is connected with system bus 310.Random access memory Device (" RAM ") 312 couples with system bus 310, makes CPU 308 can access memorizer storage 314 (may be used for the number that storage is associated with one or more parameters of nuclear fission row ripple burnfront 22 According to).When the programming instructions are executed, those process steps are stored in RAM 312 by CPU 308, and The process step of storage is performed in the outside of RAM 312.
Calculating system 306 can be via network interface 316 with by network connectivity (not shown) and calculating Machine network (not shown) connects.A kind of such network is to make calculating system 306 can download application journey The Internet of sequence, code, file and other electronic information.
Read only memory (" ROM ") 318 is provided as storing as enabled instruction sequence or basic input/defeated Go out constant job sequence as operating system (BIOS) sequence.
Input/output (" I/O ") equipment interface 320 makes the calculating system 306 can be with various input/output Equipment, such as, keyboard, location equipment (" mouse "), monitor, printer, modem etc. are even Connect.For simplicity, I/O equipment interface 320 is shown as single frame, but can include and inhomogeneity Several interfaces of the I/O equipment handing-over of type.
It will be understood that these embodiments are not limited to show the framework of calculating system 306 in figure 3b.Root According to the type of application/business environment, calculate system 306 and can contain more or less parts.Such as, meter Calculation system 306 can be Set Top Box, kneetop computer, notebook computer, desktop system or other type System.
In various embodiments, the some parts of disclosed system and method includes one or more computer Program product.Computer program includes the computer-readable recording medium as non-volatile memory medium, With embody in a computer-readable storage medium, as series of computation machine instruct computer-readable Program code sections.Generally, computer program is processed by as describing processing component in figure 3b Unit or associated storage device store and perform.
About this respect, Fig. 2 A-2M and Fig. 3 A-3C be respectively the method according to various embodiments, system, Flow chart and block diagram with program product.It will be appreciated that flow chart and each frame of block diagram and flow chart and The combination of the frame in block diagram can be realized by computer program instructions.These computer program instructions are permissible Be loaded in computer or other programmable device formation one machine, in order to computer or other can compile The instruction performed on range device forms the component of the function realizing regulation in flow chart or block diagram.These meters Calculation machine programmed instruction can also be stored in and computer or other programmable device can be instructed to rise in a specific way In the computer-readable memory of effect, in order to the instruction being stored in computer-readable memory becomes bag Include the article of the command device of the function realizing regulation in flow chart or block diagram.Computer program instructions is also Can be loaded in computer or other programmable device and make to hold on computer or other programmable device The sequence of operations step of row forms computer and realizes process, in order at computer or other programmable device The instruction of upper execution provides the step of the function realizing regulation in flow chart or block diagram.
Then, the frame support of flow chart or block diagram performs the combination of component of predetermined function, execution regulation merit The combination of the step of energy and the program instruction means of execution predetermined function.It will be understood that flow chart or frame The combination of the frame in each frame of figure and flow chart or block diagram can be by performing predetermined function or step Assembly based on specialized hardware computer system or specialized hardware and computer instruction realizes.
Referring additionally to Fig. 3 C, in certain embodiments, can be configured to determine core by circuit 304 further The existing shape of fission row ripple burnfront 22.Such as, sensor 322 can be via being properly entered interface 324 signals are operably coupled with circuit 304 communicatedly.Sensor 322 can include measuring nuclear fission row Any proper sensors of the parameter of ripple burnfront 324.Such as, sensor 322 can measure neutron Flux, neutron fluence, burnup and/or reactivity (or their any composition).
As discussed above, the embodiment of system 300 and circuit 302 and 304 can be configured to There is provided execution method 200(Fig. 2 A-2M) suitable system environments, in spite of by programmed instruction load A machine is formed, in order at computer or other dress able to programme in computer or other programmable device The instruction putting execution forms realization regulation in each frame of flow chart or block diagram or flow chart or block diagram Frame in the device of function of regulation, and flow chart or block diagram be combined through execution predetermined function or step Rapid assembly based on specialized hardware computer system or specialized hardware and computer instruction realizes. Some features of the embodiment of system 300 will be referring additionally to Figure 1B-1D, 1J, 1L, 1O, 1Q, 1R-1W Discuss with 2A-2M.
To this end, in certain embodiments, can be configured to circuit 304 further set up desired shape The mode of shape, determine fission fuel subassembly 14 selected several along the first dimension from respective first Put the migration to the respective second position.Can be configured to circuit 304 further keep desired shape Mode, determine fission fuel subassembly 14 selected several along the first dimension from respective primary importance Migration to the respective second position.Further circuit 304 can be configured to the desired shape of response Mode, determines that migrating fission fuel from respective primary importance to the respective second position along the first dimension divides Selected several time of assembly 14.
As discussed above, in certain embodiments, fission fuel subassembly 14 can be along the second dimension Degree elongation.
The most as discussed above, in certain embodiments, the first dimension can almost with fission fuel The axis of elongation of subassembly 14 is orthogonal.First dimension and the second dimension can be the most mutually orthogonal.
In various embodiments, the first dimension can include radial dimension, and the second dimension can include axle To dimension；First dimension can include axial dimension, and the second dimension can include radial dimension；First Dimension can include axial dimension, and the second dimension can include transverse dimensions；And/or first dimension permissible Including transverse dimensions, and the second dimension can include axial dimension.
In certain embodiments, primary importance can include outer position 30, and the second position can include Inner position 32.As desired, inner position 32 and outer position 30 can without limitation as based on With the geometry proximity of the core of reactor core 12, make inner position 32 based on neutron flux On neutron flux make position, the inside more than the neutron flux on outer position 30 and/or based on reactivity Put the k on 32effectiveMore than the k on outer position 30effectiveLike that based on each attribute.
In some other embodiments, primary importance can include inner position 32, and the second position is permissible Including outer position 30.As desired, inner position 32 and outer position 30 can without limitation as Based on the geometry proximity of the core of reactor core 12, make inner position based on neutron flux Neutron flux on 32 makes the inside more than the neutron flux on outer position 30 and/or based on reactivity K on position 32effectiveMore than the k on outer position 30effectiveLike that based on each attribute.At some In embodiment, primary importance and the second position can be on the opposite side of reference value along the first dimension.
In some other embodiments, primary importance and the second position can include at least substantially equalized Attribute.Such as, at least one attribute can include connecing with the geometry of the core of reactor core 12 Nearly property, neutron flux and/or reactivity.
In certain embodiments, can be configured to determine fission fuel subassembly by circuit 304 further Selected several rotation of at least one of 14.In some other embodiments, can be further by circuit 304 selected several at least one being configured to determine fission fuel subassembly 14 reverse.
As discussed above, in certain embodiments, the dimension constraint of selected group can include along second The predetermined maximal distance of dimension.
In some other embodiments, the dimension constraint of selected group can be at least one burnfront criterion Function.Such as, burnfront criterion can include without limitation: as with fission fuel subassembly Neutron flux as at least one selected several neutron flux being associated of 14；As firing with nuclear fission Neutron fluence as at least one selected several neutron fluence being associated of material subassembly 14；With/ Or as firing several at least one burnup being associated selected by fission fuel subassembly 14 Consumption.In certain embodiments, burnfront criterion can include the selected several of fission fuel subassembly 14 The burnfront position that individual at least one is interior.
In certain embodiments, can be configured to determine fission fuel subassembly by circuit 304 further 14 selected several along the first dimension from respective primary importance to the radial migration of the respective second position.Can Several along the first dimension to be configured to determine by circuit 304 further selected by fission fuel subassembly 14 Degree migrates from respective primary importance to the spiral of the respective second position.Further circuit 304 can be configured Become to determine fission fuel subassembly 14 selected several along the first dimension from respective primary importance to respectively From the axial translation of the second position.
In certain embodiments, can be configured to circuit 302 further determine nuclear fission row ripple burning battle array Face 22 approximately spherical.Can be configured to circuit 302 further determine nuclear fission row ripple burnfront The continuous bend surface configuration of 22.
In various embodiments, the desired shape of nuclear fission row ripple burnfront 22 may be about second Dimension is the most rotational symmetric；Can have the substantially n fold rotational symmetry around the second dimension；And/or Can be asymmetrical as asymmetric around the second dimension rotation without limitation.
For for another example and referring now to Fig. 4 A, another illustrative system 400 is for migrating Fission fuel subassembly (being not shown in Fig. 4 A) and provide.Given by nonrestrictive example Going out, system 400 can provide execution method 100(Figure 1A-1AF) suitable system environments.So, Make discussed below referring additionally to Figure 1A-1AF.
In certain embodiments, for the nuclear fission row ripple burnfront propagated along the first and second dimensions 22, circuit 402 is configured in fission fuel subassembly 14 according to selected group dimension retrain along Second dimension, determines the desired shape of nuclear fission row ripple burnfront 22.Circuit 404 is configured to The mode of the desired shape of response, determines the selected several along the first dimension of fission fuel subassembly 14 From respective primary importance to the migration of the respective second position.Subassembly 405 is configured to respond to circuit 404 Migrate the selected several of fission fuel subassembly 14.
It will be understood that circuit 402 and 404 can be similar to circuit 302 and 304.In some cases, Circuit 402 can be identical with circuit 302 and 304 with 404.To this end, for simplicity, it is not necessary to for Understand and repeat those details.
As general introduction and referring additionally to Fig. 4 B, in il-lustrative example, can be by circuit 402 and/or electricity Road 404 is embodied in calculating system 406(and is referred to as master computer or system).In exemplary enforcement In example, CPU (" CPU ") (or microprocessor) 408 is connected with system bus 410. Random access memory (" RAM ") 412 couples with system bus 410, makes CPU 408 to access Memorizer storage 414(may be used for one or more parameters of storage and nuclear fission row ripple burnfront 22 The data being associated).When the programming instructions are executed, those process steps are stored in RAM by CPU 408 In 412, and perform the process step of storage in the outside of RAM 412.Calculating system 406 can be via Network interface 416 and being connected with computer network (not shown) by network connectivity (not shown).Only Read memorizer (" ROM ") 418 to be provided as storing as enabled instruction sequence or basic input/output operations Constant job sequence as system (BIOS) sequence.Input/output (" I/O ") equipment interface 420 Make the calculating system 406 can be with various input-output apparatus, such as, keyboard, sensing equipment (" mouse "), Monitor, printer, modem etc. connect.It will be understood that these embodiments are not limited to show The framework of the calculating system 406 in Fig. 4 B.Without limitation for calculating system 306(Fig. 3 B) Discussion also apply be applicable to calculating system 406.
In various embodiments, the some parts of disclosed system and method includes one or more computer Program product.Above for system 300(Fig. 3 A) discussion of relevant computer program also may be used It is applied to system 400.
Divide about this respect, Figure 1A, 1I, 1K, 1M-1N, 1P, and 1X-1AF and Fig. 4 A-4C It not the method according to various embodiments, system and the flow chart of program product and block diagram.Should be understood that The combination of the frame in flow chart and each frame of block diagram and flow chart and block diagram can pass through computer program Instruction realizes.These computer program instructions can be loaded in computer or other programmable device formation One machine, in order to the instruction performed on computer or other programmable device is formed and realizes regulation at stream The component of the function in journey figure or block diagram.These computer program instructions can also be stored in and can instruct meter In the computer-readable memory that calculation machine or other programmable device work in a specific way, in order to storage Instruction in computer-readable memory becomes and includes realizing regulation function in flow chart or block diagram The article of command device.Computer program instructions can also be loaded in computer or other programmable device Make the sequence of operations step to perform on computer or other programmable device formed computer realize into Journey, in order to the instruction performed on computer or other programmable device provide realize regulation at flow chart or The step of the function in block diagram.
Then, the frame support of flow chart or block diagram performs the combination of device of predetermined function, execution regulation merit The combination of the step of energy and the program instruction means of execution predetermined function.It should also be understood that flow chart or The combination of the frame in each frame of block diagram and flow chart or block diagram can be by performing predetermined function or step Assembly based on specialized hardware computer system or specialized hardware and computer instruction realize.
Referring additionally to Fig. 4 C, in certain embodiments, can be configured to determine core by circuit 404 further The existing shape of fission row ripple burnfront 22.Such as, sensor 422 can be via being properly entered interface 324 signals are operably coupled with circuit 404 communicatedly.Circuit 404, sensor 422 and input interface 424 can be with circuit 304, sensor 322 and input interface 324(Fig. 3 C) similar (in some feelings Under condition, can be identical).Here it is unnecessary to understand and repeat their details.
As discussed above, can be by system 400, circuit 402 and 404 and the reality of subassembly 405 Execute example to be configured to and the following execution method 100(Figure 1A that the most independently provides, 1I, 1K, 1M-1N, 1P and Suitable system environments 1X-1AF): programmed instruction is loaded into shape in computer or other programmable device Cheng Yitai machine, in order to the instruction performed on computer or other programmable device is formed and realizes specifying to exist The device of the function in each frame of flow chart or block diagram or flow chart or block diagram, and flow chart or block diagram Frame be combined through perform predetermined function or step based on specialized hardware computer system or special firmly The assembly of part and computer instruction realizes.Some features of the embodiment of system 400 will be referring additionally to Figure 1A-1AF discusses.
In certain embodiments and with reference to Fig. 4 C, can be configured to determine that core splits by circuit 404 further Become the existing shape of row ripple burnfront 22.Such determine can with as it has been described above, circuit 304(figure Similar or identical mode 3A) is made.To this end, sensor 422 and input interface 424 can be with sensings Device 322 and input interface 324(Fig. 3 C) similar or the most identical.Sensor 422, Input interface 424 and circuit 404 are as above for sensor 322, input interface 324 and circuit 304 (Fig. 3 C) cooperates as being discussed.
In certain embodiments, can be configured to circuit 404 further set up the side of desired shape Formula, determine fission fuel subassembly 14 selected several along the first dimension from respective primary importance to respectively From the migration of the second position.In some other embodiments, can further circuit 404 be configured to Keep the mode of desired shape, determine the selected several along the first dimension of fission fuel subassembly 14 From respective primary importance to the migration of the respective second position.
In certain embodiments, can further circuit 404 be configured to the side of the desired shape of response Formula, determines and migrates fission fuel packet from respective primary importance to the respective second position along the first dimension Selected several time of part 14.
In certain embodiments, fission fuel subassembly 14 can be along the second dimension elongation.First dimension Degree can be almost orthogonal with the axis of elongation of fission fuel subassembly 14.First dimension and the second dimension are permissible The most mutually orthogonal.
In various embodiments, the first dimension can include radial dimension, and the second dimension can include axle To dimension；First dimension can include axial dimension, and the second dimension can include radial dimension；First Dimension can include axial dimension, and the second dimension can include transverse dimensions；And/or first dimension permissible Including transverse dimensions, and the second dimension can include axial dimension.
In certain embodiments, primary importance can include outer position 30, and the second position can include Inner position 32.Inner position 32 and outer position 30 can be based on: with in reactor core 12 The geometry proximity of heart part；Neutron flux makes the neutron flux on inner position 32 more than outer position Neutron flux on 30；And/or reactivity makes the k on inner position 32effectiveMore than outer position 30 On keffective。
In some other embodiments, primary importance can include inner position 32, and the second position is permissible Including outer position 30.Inner position and outer position can be based on the central parts with reactor core 12 The geometry proximity divided；Make the neutron flux on inner position 32 more than outer position based on neutron flux Neutron flux on 30；And/or make the k on inner position 32 based on reactivityeffectiveMore than position, outside Put the k on 30effective。
In certain embodiments, primary importance and the second position can be in reference value along the first dimension On opposite side.
In some other embodiments, primary importance and the second position can include at least substantially equalized Attribute.Such as, at least one attribute can include connecing with the geometry of the central area of reactor core 12 Nearly property；Neutron flux；And/or it is reactive.
In various embodiments, can be configured to determine fission fuel subassembly by circuit 404 further Selected several rotation of at least one of 14.Can be configured to determine nuclear fission by circuit 404 further Overturning of selected several at least one of fuel subassembly 14.
Subassembly 405 can include without limitation as reactor core kernel fuel-management device, existing Known any suitable nuclear fuel management device in technology.But, in some other embodiments, packet Part 405 can include reactor core outer core fuel-management device.
Unrelated with the form that subassembly 405 is embodied, in various embodiments, can will divide further Assembly 405 is configured to from respective primary importance to respective second position radial migration fission fuel subassembly 14 selected several.Further subassembly 405 can be configured to from respective primary importance to respective second Position spiral migrates the selected several of fission fuel subassembly 14.Further subassembly 405 can be joined It is set to the selected several of axial translation fission fuel subassembly 14.
In certain embodiments, can be configured to subassembly 405 further rotate fission fuel packet Part 14 selected several.In some other embodiments, further subassembly 405 can be configured to top The subassembly of falling fission fuel 14 selected several.Referring now to Fig. 5, in various embodiments, permissible Exemplary nuclear fission row ripple reactor 500 is provided.Nuclear fission row ripple reactor 500 includes nuclear fission row ripple Reactor core 12.As discussed above, nuclear fission row ripple reactor core 12 is received nuclear fission Fuel subassembly 14.It is configured to each fission fuel subassembly 14 make nuclear fission row ripple burnfront 22 propagate along the first and second dimensions wherein.Circuit 402 is configured at fission fuel subassembly In 14, the dimension according to selected group retrains along the second dimension, determines nuclear fission row ripple burnfront 22 Desired shape.It is configured to circuit 404 in the way of the desired shape of response determine, fission fuel Subassembly 14 selected several along the first dimension from respective primary importance to the migration of the respective second position. Subassembly 405 is configured to respond to circuit 404, migrates the selected several of fission fuel subassembly 14.
Therefore, it can be embodied in reactor 500 be combined with system 400 discussed above and cooperate Also as discussed above reactor core 12.Because have been directed towards above reactor core 12(and Parts) and system 400(and parts thereof) give details, so without repeating details to understand.
As have been discussed above, in various embodiments, can be further by circuit 404 It is configured to determine the existing shape of nuclear fission row ripple burnfront 22.Further circuit 404 can be configured Become in the way of setting up desired shape, determine the selected several along first of fission fuel subassembly 14 Dimension from respective primary importance to the migration of the respective second position.Further circuit 404 can be configured to In the way of maintaining desired shape, determine the selected several along the first dimension of fission fuel subassembly 14 Spend from respective primary importance to the migration of the respective second position.
As discussed above, in certain embodiments, can further circuit 404 be configured to response The mode of desired shape, determines and migrates to the respective second position from respective primary importance along the first dimension Selected several time of fission fuel subassembly 14.
In certain embodiments, fission fuel subassembly 14 can be along the second dimension elongation.
In certain embodiments, the first dimension can almost with the axis of elongation of fission fuel subassembly 14 just Hand over.In certain embodiments, the first dimension and the second dimension can be the most mutually orthogonal.
In various embodiments, the first dimension can include radial dimension, and the second dimension can include axle To dimension；First dimension can include axial dimension, and the second dimension can include radial dimension；First Dimension can include axial dimension, and the second dimension can include transverse dimensions；And/or first dimension permissible Including transverse dimensions, and the second dimension can include axial dimension.
In certain embodiments, primary importance can include outer position 30, and the second position can include Inner position 32.Inner position 32 and outer position 30 can be based on the centers with reactor core 12 The geometry proximity of part；Neutron flux makes the neutron flux on inner position 32 more than outer position Neutron flux on 30；And/or reactivity makes the k on inner position 32effectiveMore than outer position 30 On keffective。
In some other embodiments, primary importance can include inner position 32, and the second position is permissible Including outer position 30.Inner position 32 and outer position 30 can based on reactor core 12 The geometry proximity of core；Neutron flux makes the neutron flux on inner position 32 more than position, outside Put the neutron flux on 30；And/or reactivity makes the k on inner position 32effectiveMore than outer position K on 30effective。
In certain embodiments, primary importance and the second position can be in reference value along the first dimension On opposite side.
In some other embodiments, primary importance and the second position can include at least substantially equalized Attribute.Such as, at least one attribute can include connecing with the geometry of the central area of reactor core 12 Nearly property；Neutron flux；And/or it is reactive.
In various embodiments and as discussed above, can be configured to determine by circuit 404 further Selected several rotation of at least one of fission fuel subassembly 14, and/or be further configured to really Determine selected several at least one reverse of fission fuel subassembly 14.
In certain embodiments, the dimension constraint of selected group can include the predetermined maximum along the second dimension Distance.In some other embodiments, the dimension of selected group constraint can be without limitation as following that The function of at least one burnfront criterion of sample: as with fission fuel subassembly 14 selected by several Neutron flux as at least one neutron flux being associated；As the institute with fission fuel subassembly 14 Select neutron fluence as the neutron fluence that several at least one be associated；And/or as and fission fuel Burnup as at least one selected several burnup being associated of subassembly 14.At some, other is implemented In example, in burnfront criterion can include selected several at least one of fission fuel subassembly 14 Burnfront position.
In various embodiments, can be configured to determine fission fuel subassembly by circuit 404 further 14 selected several along the first dimension from respective primary importance to the radial migration of the respective second position.Can Several along the first dimension to be configured to determine by circuit 404 further selected by fission fuel subassembly 14 Degree migrates from respective primary importance to the spiral of the respective second position.Further circuit 404 can be configured Become to determine selected several axial translation of fission fuel subassembly 14,
In various embodiments, can be configured to circuit 402 further determine nuclear fission row ripple burning battle array Approximately spherical and/or the continuous bend surface configuration of nuclear fission row ripple burnfront 22 in face 22.Core splits It is the most rotational symmetric that the desired shape of change row ripple burnfront 22 may be about the second dimension；Permissible There is the substantially n fold rotational symmetry around the second dimension；And/or can be as rotating around the second dimension Asymmetric such asymmetrical.
In certain embodiments, subassembly 405 can include nuclear fuel management device.As discussed above, Subassembly 405 can include without limitation as reactor core kernel fuel-management device, in prior art Any suitable nuclear fuel management device known in.But, in some other embodiments, subassembly 405 Reactor core outer core fuel-management device can be included.
The most as discussed above, in various embodiments, can further subassembly 405 be configured to From respective primary importance to several selected by respective second position radial migration fission fuel subassembly 14. Can be configured to subassembly 405 further migrate core from respective primary importance to respective second position spiral Fission fuel subassembly 14 selected several.Further subassembly 405 can be configured to axial translation core Fission fuel subassembly 14 selected several.Can be configured to subassembly 405 further rotate nuclear fission Fuel subassembly 14 selected several.Further subassembly 405 can be configured to reverse fission fuel Subassembly 14 selected several.
Referring now to Fig. 6 A, in certain embodiments, it is provided that the method for operation nuclear fission row ripple reactor 600.Method 600 is from the beginning of frame 602.Referring additionally to Figure 1B, in block 604, by least one core The fission fuel subassembly 14 primary importance from nuclear fission row ripple reactor core 12 outwards moves to core The second position in fission row ripple reactor core 12.The method 600 is terminated in frame 606.
In certain embodiments and referring additionally to Fig. 6 B, in block 608, can be inside from the second position Migrate at least one fission fuel subassembly 14.
In various embodiments, primary importance and the second position can be based on the centers with reactor core 12 The geometry proximity of part；Make the neutron flux in primary importance more than the second position based on neutron flux On neutron flux；And/or the k in primary importance is made based on reactivityeffectiveMore than in the second position keffective。
Referring now to Fig. 7, in certain embodiments, it is provided that the method for operation nuclear fission row ripple reactor 700.Method 700 is from the beginning of frame 702.Referring additionally to Figure 1B, in block 704, at least one is determined Fission fuel subassembly 14, in a first direction first from nuclear fission row ripple reactor core 12 Put the migration of the second position in nuclear fission row ripple reactor core 12.The second position is different from first Put.In frame 706, determine at least one fission fuel subassembly 14 in second direction from the second position Migration.Second direction is different from first direction.The method 700 is terminated in frame 708.
In certain embodiments, first direction can be outside, and second direction can be inside.Primary importance Can be based on without limitation as attribute as following or parameter with the second position: with reactor core 12 The geometry proximity of core；Neutron flux makes the neutron flux in primary importance more than second The neutron flux put；And/or reactivity makes the k in primary importanceeffectiveMore than in the second position keffective。
In certain embodiments, first direction can be inside, and second direction can be outside.The second position Can be based on without limitation as attribute as following or parameter with primary importance: with reactor core 12 The geometry proximity of core；Neutron flux makes the neutron flux in the second position more than first The neutron flux put；And/or reactivity makes the k in the second positioneffectiveMore than in primary importance keffective。
Referring now to Fig. 8, in certain embodiments, it is provided that the method for operation nuclear fission row ripple reactor 800.Method 800 is from the beginning of frame 802.Referring additionally to Figure 1B, in frame 804, by least one core Fission fuel subassembly 14, the in a first direction primary importance from nuclear fission row ripple reactor core 12 Move to the second position in nuclear fission row ripple reactor core 12.The second position is different from primary importance. In frame 806, determine that at least one fission fuel subassembly 14 is second direction moving from the second position Move.Second direction is different from first direction.Terminate the method 800 in block 808.
In certain embodiments, first direction can be outside, and second direction can be inside.Primary importance Can be based on without limitation as attribute as following or parameter with the second position: with reactor core 12 The geometry proximity of core；Neutron flux makes the neutron flux in primary importance more than second The neutron flux put；And/or reactivity makes the k in primary importanceeffectiveMore than in the second position keffective。
In certain embodiments, first direction can be inside, and second direction can be outside.The second position Can be based on without limitation as attribute as following or parameter with primary importance: with reactor core 12 The geometry proximity of core；Neutron flux makes the neutron flux in the second position more than first The neutron flux put；And/or reactivity makes the k in the second positioneffectiveMore than in primary importance keffective。
Referring now to Fig. 9, in certain embodiments, it is provided that the method for operation nuclear fission row ripple reactor 900.Method 900 is from the beginning of frame 902.Referring additionally to Figure 1B, in frame 904, by least one core Fission fuel subassembly 14, the in a first direction primary importance from nuclear fission row ripple reactor core 12 Move to the second position in nuclear fission row ripple reactor core 12.The second position is different from primary importance. In frame 906, migrate at least one fission fuel subassembly 14 in second direction from the second position.The Two directions are different from first direction.The method 900 is terminated in frame 908.
In certain embodiments, first direction can be outside, and second direction can be inside.Primary importance Can be based on without limitation as attribute as following or parameter with the second position: with reactor core 12 The geometry proximity of core；Neutron flux makes the neutron flux in primary importance more than second The neutron flux put；And/or reactivity makes the k in primary importanceeffectiveMore than in the second position keffective。
In certain embodiments, first direction can be inside, and second direction can be outside.The second position Can be based on without limitation as attribute as following or parameter with primary importance: with reactor core 12 The geometry proximity of core；Neutron flux makes the neutron flux in the second position more than first The neutron flux put；And/or reactivity makes the k in the second positioneffectiveMore than in primary importance keffective。
Referring now to Figure 10 A, in certain embodiments, it is provided that the side of operation nuclear fission row ripple reactor Method 1000.Method 1000 is from the beginning of frame 1002.In frame 1004, select predetermined burn up level.? In frame 1006, all to reach the burnup equal to predetermined burn up level in nearly all fission fuel assemblies The mode of level, determines selected several migration of fission fuel assemblies in fission-type reactor reactor core. The method 1000 is terminated in frame 1008.
Referring additionally to Figure 10 B, in certain embodiments, in frame 1010, can be determined with response and be moved The mode moved, migrates the selected several of fission fuel assemblies in fission-type reactor reactor core.
Referring additionally to Figure 10 C, in certain embodiments, in frame 1012, when burn up level is equal to predetermined During burn up level, it may be determined that the most selected several by fission fuel assemblies remove.
Referring additionally to Figure 10 D, in certain embodiments, in frame 1014, remove determined by response, The selected several of fission fuel assemblies can be removed.
For the sake of clearly showing, the application employs pro forma generality title.However, it should Understanding, these generality titles, for the purpose shown, can be discussed different types of in whole application Theme is (for example, it is possible to describe equipment/structure and/or can be at structure/process mark under process/operation title Process/operation is discussed under topic；And/or the description of single topic can cross over two or more topic titles). Therefore, the use of pro forma generality title is in no way intended to limit the scope of the present invention.
Those of ordinary skill in the art is it will be understood that particular exemplary process, equipment and/or technology above Represent as other in the claims submitted to herein and/or in the application is local, herein More typically process, equipment and/or the technology that other place is told about.
It is appreciated by those skilled in the art that prior art has advanced at each of system Almost without the stage of what difference between the hardware of aspect, software and/or firmware realization；Hardware, software And/or the use of firmware general (but may not because in some contexts, make between hardware and software Select the most meaningful) it is to represent the design alternative of balance between cost and efficiency.This area common Technical staff is it will be understood that exist and can realize the various of process as herein described, system and/or other technology Instrument (such as, hardware, software and/or firmware), and preferred kit with deployment process, system and/or The background of other technology and become.Such as, if implementor determine speed and precision it is critical that, then Implementor can select main hardware and/or firmware vehicle；On the other hand, if motility is most important , then implementor can select main software to realize；Or, another further aspect, it is achieved person can select firmly Certain assembly of part, software and/or firmware.Accordingly, there exist and can realize process as herein described, set Standby and/or other technology several may instruments, do not have a kind of instrument sky to be born with and be better than other instrument because Any instrument to be utilized all is depending on background and the realization of any deployment tool that all may change The option of the special concern (such as, speed, motility or predictable) of person.The common skill of this area Art personnel should be realized that, it is achieved the commonly used hardware relevant with optics of optics aspect, software and/or Firmware.
In embodiments more as herein described, logic can include software or other control with similar realization Structure.Circuit can contain, and such as, builds for realizing various function as described herein and arranges One or more path of electric current.In some implementations, one or more media can be configured to when this The medium of sample preserves or sends can play to undertake when the equipment of execution effect as described herein can detect instruction and sets For detecting realization.In some variants, such as, some realize can including as by carrying out with herein The reception of one or more instruction that described one or many operation is relevant or transmission like that, update or repair Change existing software or firmware or gate array or programmable hardware.Alternately, or it addition, at some In variant, a kind of realize including special-purpose software, software, firmware component and/or perform or otherwise Call the universal component of special-purpose member.Some specifications or other realization can be by the most tangible One or more examples of transmission medium, alternatively, are transmitted by packet, or otherwise by various Time transmits through distributed medium.
Alternately, or it addition, some realize can include perform special instruction sequence or call permission, Trigger, coordinate, ask or otherwise cause substantially any feature operation as herein described once or many The circuit of secondary generation.In some variants, operation herein or other logical description can be expressed as source Code, and be compiled into executable instruction sequence or otherwise call as executable instruction sequence.One In a little variants, such as, some realizations can be completely or partially by source code as C++ or other generation Code sequence provides.In other realizes, can will use commercial product and/or of the prior art various The source code of technology or other code realize compiling/realize/translate/be converted into high level description language (such as, Initial C or C++ programming language realizes described technology, hereafter realizes being converted into and can patrolling by programming language Volume synthetic language realizes, hardware description language realizes, hardware designs the Realization of Simulation and/or other is such Similar expression way).For example, it is possible to by some or all of logical expressions (such as, computer programming language Realize) be expressed as Verilog type hardware description (such as, via hardware description language (HDL) and/or VHSIC hardware description language (VHDL)) probable after may be used for creating containing hardware (example Such as, specific store circuit) other circuit model of physics realization.Those of ordinary skill in the art should This is recognized and how to obtain according to these teachings, configure and optimize suitably transmission or computing element, goods and materials, Actuator or other structure.
Detailed descriptions above illustrates equipment and/or process by using block diagram, flow chart and/or example Various embodiments.One or more functions and/or operation are comprised at such block diagram, flow chart and/or example In the case of, it will be understood by those skilled in the art that at such block diagram, flow chart or example In every kind of function and/or operation can pass through diversified hardware, software, firmware or they almost Any combination is individually and/or collective realizes.In one embodiment, several parts of theme as herein described Can pass through at special IC (ASIC), field programmable gate array (FPGA), digital signal Reason device (DSP) or other integrated form realize.But, those of ordinary skill in the art should recognize Knowledge is arrived, and some aspects of embodiment disclosed herein can be the most equivalent real The ready-made one or more computer programs operated on one or more computer are (such as, it is achieved Cheng Yun The row one or more programs in one or more computer systems), it is achieved become to operate in one or more One or more programs on processor are (such as, it is achieved become to operate on one or more microprocessor One or more programs), it is achieved one-tenth firmware, or it is implemented as their substantially any combination, and design electricity Road and/or for software and/or firmware write code one skilled in the relevant art all completely technical ability it In.It addition, those of ordinary skill in the art is it will be understood that the mechanism of theme as herein described can conduct Program product is distributed with diversified form, and the exemplary embodiments of theme as herein described and use Particular type in the actual signal bearing medium being distributed independently is applied.The example of signal bearing medium Son includes but not limited to following medium: as floppy disk, hard disk drive, compact disc (CD), numeral regard Frequently such recordable type medium such as dish (DVD), digital magnetic tape, computer storage；And as numeral and / or analogue communication medium (such as, Connectorized fiber optic cabling, waveguide, wired communications links, wireless communication link (example Such as, transmitter, receiver, transmitting logical block, receive logical block etc.) etc.) as mode transmission Medium.
It is, in general, that it is appreciated by those skilled in the art that embodiment as herein described is permissible By various types of Mechatronic Systems, individually and/or collective realizes, this Mechatronic Systems contain as hardware, software, Firmware and/or varied electricity parts of their substantially any combination；And as rigid body, elasticity or torsion Body, hydraulic system, Electromagnetically actuated equipment and/or their substantially any combination can transmit mechanical force like that Or varied parts of motion.Therefore, as used throughout, " Mechatronic Systems " include but not limited to can Operatively with transducer (such as, actuator, motor, piezoquartz, MEMS (MEMS) Deng) circuit that couples, circuit containing at least one discrete circuit, containing at least one integrated circuit The general meter that circuit, the circuit containing at least one special IC, formation are made up of computer program Calculation equipment (such as, is made up of the computer program at least partly realizing process as herein described and/or equipment General purpose computer or by the computer program structure at least partly realizing process as herein described and/or equipment Become microprocessor) circuit, formed storage device (such as, various forms (such as, random access memory, Flash, read-only etc.) memorizer) circuit, form communication equipment (such as, modem, logical Letter switch, opto-electronic conversion equipment etc.) circuit and/or any non-as light or other analog Electricity analog.Those of ordinary skill in the art it will also be understood that, the example of electric system includes but not limited to Consumer electronics system miscellaneous, armarium, and as motorized transport systems, factory automation System, security system and/or the communication/system that calculates other system such.The ordinary skill people of this area Member is it should be appreciated that as used herein Mechatronic Systems is not necessarily limited to have electric actuation and mechanically actuated Both systems, unless otherwise indicated by context.
With this specification about and/or be listed in all above United States Patent (USP) in any request for data table, the U.S. Patent application Publication, U.S. Patent application, foreign patent, foreign patent application and non-patent announcement all with It is not herein incorporated by reference with the most inconsistent degree.
It is appreciated by those skilled in the art that elements illustrated herein (such as, operation), set Standby, object and be used as the example of clarification concept with discussing of they, it can be envisaged that go out various configuration modification. Therefore, as used herein, the specific examples of displaying and adjoint discussion are intended to represent their more one As classification.It is, in general, that the use of any specific examples is intended to represent its classification, and particular portion Part (such as, operation), equipment and object do not include not being considered as limiting property.
About substantially any plural number used herein and/or singular references, those of ordinary skill in the art is Proportionately plural number can be changed into odd number with context and/or application and/or odd number is changed into plural number.In order to clearly For the sake of clear, various singular/plural displacement is not explicitly shown herein.
Theme as herein described sometimes illustrates and is included in other different parts, or parts different from other The different parts connected.Should be understood that what the framework so described was merely an illustrative, it is true that can To realize many other frameworks realizing identical function.From concept, effectively realization " is associated " Any arrangement of the parts of identical function, in order to realize desired function.Therefore, combine herein Any two parts realizing specific function are considered as mutually " associating " so that with framework or intermediate member Independently realize desired function.Equally, any two parts of so association can also regard as realizing institute Wish mutual " being operably connected " or " being operatively coupled " of function, and can so associate Any two parts can also regard as realizing mutual " operably coupled " of desired function.Operably coupled Special case include but not limited to physically can to match and/or physically interact parts, can wireless phase interaction With and/or wireless interaction parts and/or in logic interact and or/can interact portion in logic Part.
Although it has been shown and described that the particular aspects of current topic as herein described, but for this area Those of ordinary skill for, it is therefore apparent that can be according to teaching herein, without departing from as herein described Making to theme and broader aspect thereof change and amendment, therefore, appended claims will be as herein The true spirit of described theme and within the scope of such all such changes and amendment be included in its model Within enclosing.It will be understood by those skilled in the art that it is, in general, that with in this article, especially use Term in described claims (such as, the major part of appended claims) is generally intended to As open to the outside world term (such as, gerund term " include " being construed as gerund " include but It is not limited to ", gerund term " contains " and is construed as gerund and " at least contains ", verb term " bag Include " be construed as verb and " include but not limited to ").Those of ordinary skill in the art also should be bright In vain, if having a mind to represent certain amount of introduced claim recitation item, the most in the claims by bright Really enumerate such intention, and in the case of lacking such enumerating, the most there is not such intention. Such as, in order to help it is appreciated that, following appended claims may comprise use introductory phrase " extremely Few one " and " one or more " introduce claim recitation item.But, even if same right Require to include introductory phrase " one or more " or " at least one " and as " one " or " one Kind " (such as, " one " and/or " a kind of " be generally understood that " at least one " or " one or Multiple " the meaning) as indefinite article, the use of such phrase also should not be construed imply logical Cross indefinite article " " or " a kind of " introduces claim recitation item and will comprise introduced right Any specific rights requiring listed item requires to be limited in the claim only comprising such listed item On；For the use of the definite article for introducing claim recitation item, this sets up equally.It addition, i.e. Making clearly to list certain amount of introduced claim recitation item, those of ordinary skill in the art is also It should be appreciated that such enumerating is generally understood that at least have the meaning of cited quantity (such as, In the case of there is no other qualifier, only enumerate " two listed item " and generally mean that at least two arranges Lift item, or two or more listed item).And, it is similar in use that " A, B and C etc. are extremely Few one " usage in the case of, it is, in general, that such structure is intended to the general of this area Lead to and use (such as, " containing A, B and C at least in the sense that artisans understand that this usage The system of one " will include but not limited to comprise only A, comprise only B, comprise only C, contain A together And B, contain A and C together, contain B and C together, and/or contain A, B and C etc. together be System).In the case of use is similar to the usage of " at least one of A, B or C etc. ", It is, in general, that such structure is intended in the sense that those of ordinary skill in the art understands this usage Use and (such as, will include but not limited to comprise only " containing the system of at least one of A, B or C " A, comprises only B, comprises only C, contains A and B together, contains A and C together, contains B together And C, and/or contain the system of A, B and C etc. together).Those of ordinary skill in the art also should Understand generally, no matter in description, claims or accompanying drawing, occur that two or more can replace Separation word and/or phrase for project should be understood to have and include one of these projects, appointing of these projects One, or the probability of two projects, unless otherwise indicated by context.Such as, phrase " A or B " It is usually understood as including " A ", " B " or the probability of " A and B ".
About appended claims, those of ordinary skill in the art is it will be understood that behaviour cited herein Make typically can be performed in any order.Although additionally, various operating process displays in order, but Should be understood that various operation can be performed by other order different from illustrated order, or permissible Perform simultaneously.The example of the most alternative sequence can include overlap, interlock, block, reset, be incremented by, Preparation, supplement, simultaneously, reversely or other derivative sequence, unless otherwise indicated by context.And, As " response ... ", " with ... relevant " or other past tense adjective as term be typically not intended to repel so Derivative, unless otherwise indicated by context.
Some aspects of theme as herein described display with following numbering provision:
1. the method operating nuclear fission row ripple reactor, described method comprises:
In multiple fission fuel subassemblies in the reactor core of nuclear fission row ripple reactor, make core Fission row ripple burnfront is propagated along the first and second dimensions；And
To retrain the shape limiting nuclear fission row ripple burnfront along the second dimension according to the dimension of selected group Mode, along the first dimension from respective primary importance to the multiple nuclear fission of controlled migration of the respective second position Fuel subassembly selected several.
2. the method as described in provision 1, plurality of fission fuel subassembly extends along the second dimension.
3. the method as described in provision 1, wherein the first dimension almost with multiple fission fuel subassemblies The axis of elongation is orthogonal.
4. the method as described in provision 1, wherein the first dimension and the second dimension are the most mutually orthogonal.
5. the method as described in provision 1, wherein:
First dimension includes radial dimension；And
Second dimension includes axial dimension.
6. the method as described in provision 1, wherein:
First dimension includes axial dimension；And
Second dimension includes radial dimension.
7. the method as described in provision 1, wherein:
First dimension includes axial dimension；And
Second dimension includes transverse dimensions.
8. the method as described in provision 1, wherein:
First dimension includes transverse dimensions；And
Second dimension includes axial dimension.
9. the method as described in provision 1, wherein:
Primary importance includes outer position；And
The second position includes inner position.
10. the method as described in provision 9, wherein inner position and outer position based on reactor core The geometry proximity of core.
11. methods as described in provision 9, wherein inner position and outer position are based on neutron flux, make Obtain the neutron flux on inner position more than the neutron flux on outer position.
12. methods as described in provision 9, wherein inner position and outer position are based on reactivity so that K on inner positioneffectiveMore than the k on outer positioneffective。
13. methods as described in provision 1, wherein:
Primary importance includes inner position；And
The second position includes outer position.
14. methods as described in provision 13, wherein inner position and outer position based on reactor core The geometry proximity of core.
15. methods as described in provision 13, wherein inner position and outer position are based on neutron flux, make Obtain the neutron flux on inner position more than the neutron flux on outer position.
16. methods as described in provision 13, wherein inner position and outer position are based on reactivity so that K on inner positioneffectiveMore than the k on outer positioneffective。
17. methods as described in provision 1, wherein primary importance and the second position are in along the first dimension On the opposite side of reference value.
18. methods as described in provision 1, wherein primary importance and the second position include substantially equalizing to A few attribute.
19. methods as described in provision 18, at least one of which attribute includes the center with reactor core The geometry proximity in region.
20. methods as described in provision 18, at least one of which attribute includes neutron flux.
21. methods as described in provision 18, at least one of which attribute includes reactivity.
22. methods as described in provision 1, wherein along the first dimension from respective primary importance to respective Two positions, rotate multiple nuclear fission combustion selected several the including of controlled migration multiple fission fuel subassembly Selected several at least one of material subassembly.
23. the method as described in provision 1, wherein along the first dimension from respective primary importance to respective Two positions, the selected several of controlled migration multiple fission fuel subassembly include reverse multiple nuclear fissions combustion Selected several at least one of material subassembly.
24. methods as described in provision 1, wherein the dimension constraint of selected group includes along the second dimension Predetermined maximal distance.
25. methods as described in provision 1, wherein the dimension constraint of selected group is at least one burnfront The function of criterion.
26. methods as described in provision 25, wherein burnfront criterion includes neutron flux.
27. methods as described in provision 26, wherein by neutron flux and multiple fission fuel subassemblies Selected several at least one is associated.
28. methods as described in provision 25, wherein burnfront criterion includes neutron fluence.
29. methods as described in provision 28, wherein by neutron fluence and multiple fission fuel subassemblies Selected several at least one is associated.
30. methods as described in provision 25, wherein burnfront criterion includes burnup.
31. methods as described in provision 30, wherein by selected by burnup and multiple fission fuel subassemblies Several at least one is associated.
32. methods as described in provision 25, wherein burnfront criterion includes that multiple fission fuel is grouped At least one selected several interior burnfront position of part.
33. methods as described in provision 1, wherein along the first dimension from respective primary importance to respective Selected several the including of the two controlled migration in position multiple fission fuel subassemblies: along the first dimension from respectively From primary importance to several selected by the most controlled migration of the respective second position multiple fission fuel subassembly Individual.
34. the method as described in provision 1, wherein along the first dimension from respective primary importance to respective Selected several the including of the two controlled migration in position multiple fission fuel subassemblies: along the first dimension from respectively From primary importance to several selected by the most controlled migration of the respective second position multiple fission fuel subassembly Individual.
35. methods as described in provision 1, wherein along the first dimension from respective primary importance to respective Selected several the including of the two controlled migration in position multiple fission fuel subassemblies: along the first dimension from respectively From primary importance to several selected by the most controlled migration of the respective second position multiple fission fuel subassembly Individual.
36. methods as described in provision 1, wherein the shape of nuclear fission row ripple burnfront is approximately spherical 's.
37. methods as described in provision 1, the wherein shape of nuclear fission row ripple burnfront and selected line Curved surface is substantially consistent.
38. methods as described in provision 1, wherein the shape of nuclear fission row ripple burnfront is around second Dimension is the most rotational symmetric.
39. methods as described in provision 1, wherein the shape of nuclear fission row ripple burnfront has around The substantially n fold rotational symmetry of two-dimensions.
40. methods as described in provision 1, wherein nuclear fission row ripple burnfront is along the shape of the second dimension Shape is asymmetrical.
41. methods as described in provision 40, wherein the shape of nuclear fission row ripple burnfront is around second Dimension is rotationally asymmetric.
42. methods as described in provision 1, comprise further and utilize multiple nuclear fission row ripple ignition module to draw Send out nuclear fission row ripple burnfront.
43. methods as described in provision 42, further contained in along the first dimension from respective primary importance Before several selected by the controlled migration of the respective second position multiple fission fuel subassembly, remove multiple At least one of nuclear fission row ripple ignition module.
44. methods as described in provision 43, wherein along the first dimension from respective primary importance to each The controlled migration of the second position multiple fission fuel subassembly selected several before, remove multiple nuclear fission At least one of row ripple ignition module includes: along the first dimension from respective primary importance to respective second The controlled migration in position multiple fission fuel subassembly selected several before, remove many from the second position At least one of individual nuclear fission row ripple ignition module.
45. methods as described in provision 1, comprise further: make nuclear fission row ripple reactor along Dimension from respective primary importance to the institute of the controlled migration of the respective second position multiple fission fuel subassembly Select several before, become subcritical.
46. methods as described in provision 45, wherein make nuclear fission row ripple reactor become subcritical include by In neutron absorber material insertion reaction heap reactor core.
47. methods as described in provision 45, comprise further: along the first dimension from respective first Put after several selected by the controlled migration of the respective second position multiple fission fuel subassembly, again build Vertical critical.
48. methods as described in provision 47, wherein re-establish critical including: move from reactor core At least part of except neutron absorber material.
49. methods as described in provision 45, comprise further: along the first dimension from respective first Put before several selected by the controlled migration of the respective second position multiple fission fuel subassembly, close closed kernel Fission row ripple reactor.
50. methods as described in provision 49, comprise further: along the first dimension from respective first Put after several selected by the controlled migration of the respective second position multiple fission fuel subassembly, again open Kinetonucleus fission row ripple reactor.
51. 1 kinds of methods controlling fission fuel reactor, described method comprises:
For the nuclear fission row ripple burnfront propagated along the first and second dimensions, fire in multiple nuclear fissions In material subassembly, the dimension according to selected group retrains along the second dimension, determines nuclear fission row ripple burnfront Desired shape；And
In the way of the desired shape of response, determine multiple fission fuel subassembly selected several along First dimension from respective primary importance to the migration of the respective second position.
52. methods as described in provision 51, comprise further:
Determine the existing shape of nuclear fission row ripple burnfront.
53. methods as described in provision 51, wherein in the way of the desired shape of response, determine multiple core Fission fuel subassembly selected several along the first dimension from respective primary importance to the respective second position Migration includes: in the way of setting up desired shape, determine the selected several of multiple fission fuel subassembly Individual along the first dimension from respective primary importance to the migration of the respective second position.
54. methods as described in provision 51, wherein in the way of the desired shape of response, determine multiple core Fission fuel subassembly selected several along the first dimension from respective primary importance to the respective second position Migration includes: in the way of maintaining desired shape, determine the selected several of multiple fission fuel subassembly Individual along the first dimension from respective primary importance to the migration of the respective second position.
55. methods as described in provision 51, comprise further:
In the way of the desired shape of response, determine along the first dimension from respective primary importance to respective the Two positions migrate selected several time of multiple fission fuel subassemblies.
56. methods as described in provision 51, comprise further:
In the way of the desired shape of response, along the first dimension from respective primary importance to respective second Put and migrate the selected several of multiple fission fuel subassemblies.
57. methods as described in provision 51, plurality of fission fuel subassembly is stretched along the second dimension Long.
58. methods as described in provision 51, wherein the first dimension almost with multiple fission fuel subassemblies The axis of elongation orthogonal.
59. methods as described in provision 51, wherein the first dimension and the second dimension are the most mutually orthogonal.
60. methods as described in provision 51, wherein:
First dimension includes radial dimension；And
Second dimension includes axial dimension.
61. methods as described in provision 51, wherein:
First dimension includes axial dimension；And
Second dimension includes radial dimension.
62. methods as described in provision 51, wherein:
First dimension includes axial dimension；And
Second dimension includes transverse dimensions.
63. methods as described in provision 51, wherein:
First dimension includes transverse dimensions；And
Second dimension includes axial dimension.
64. methods as described in provision 51, wherein:
Primary importance includes outer position；And
The second position includes inner position.
65. methods as described in provision 64, wherein inner position and outer position based on reactor core The geometry proximity of core.
66. methods as described in provision 64, wherein inner position and outer position are based on neutron flux, make Obtain the neutron flux on inner position more than the neutron flux on outer position.
67. methods as described in provision 64, wherein inner position and outer position are based on reactivity so that K on inner positioneffectiveMore than the k on outer positioneffective。
68. methods as described in provision 51, wherein:
Primary importance includes inner position；And
The second position includes outer position.
69. methods as described in provision 68, wherein inner position and outer position based on reactor core The geometry proximity of core.
70. methods as described in provision 68, wherein inner position and outer position are based on neutron flux, make Obtain the neutron flux on inner position more than the neutron flux on outer position.
71. methods as described in provision 68, wherein inner position and outer position are based on reactivity so that K on inner positioneffectiveMore than the k on outer positioneffective。
72. methods as described in provision 51, wherein primary importance and the second position are in along the first dimension On the opposite side of reference value.
73. methods as described in provision 51, wherein primary importance and the second position include substantially equalizing to A few attribute.
74. methods as described in provision 73, at least one of which attribute includes the center with reactor core The geometry proximity in region.
75. methods as described in provision 73, at least one of which attribute includes neutron flux.
76. methods as described in provision 73, at least one of which attribute includes reactivity.
77. methods as described in provision 51, wherein determine the selected several of multiple fission fuel subassembly Multiple nuclear fission is comprised determining that from respective primary importance to the migration of the respective second position along the first dimension Selected several rotation of at least one of fuel subassembly.
78. methods as described in provision 51, wherein determine the selected several of multiple fission fuel subassembly Multiple nuclear fission is comprised determining that from respective primary importance to the migration of the respective second position along the first dimension Overturning of selected several at least one of fuel subassembly.
79. methods as described in provision 51, wherein the dimension constraint of selected group includes along the second dimension Predetermined maximal distance.
80. methods as described in provision 51, wherein the dimension constraint of selected group is at least one burnfront The function of criterion.
81. methods as described in provision 80, wherein burnfront criterion includes neutron flux.
82. methods as described in provision 81, wherein by neutron flux and multiple fission fuel subassemblies Selected several at least one is associated.
83. methods as described in provision 80, wherein burnfront criterion includes neutron fluence.
84. methods as described in provision 83, wherein by neutron fluence and multiple fission fuel subassemblies Selected several at least one is associated.
85. methods as described in provision 80, wherein burnfront criterion includes burnup.
86. methods as described in provision 85, wherein by selected by burnup and multiple fission fuel subassemblies Several at least one is associated.
87. methods as described in provision 80, wherein burnfront criterion includes that multiple fission fuel is grouped At least one selected several interior burnfront position of part.
88. methods as described in provision 51, wherein determine the selected several of multiple fission fuel subassembly Multiple nuclear fission is comprised determining that from respective primary importance to the migration of the respective second position along the first dimension Fuel subassembly selected several along the first dimension from respective primary importance to the radial direction of the respective second position Migrate.
89. methods as described in provision 51, wherein determine the selected several of multiple fission fuel subassembly Multiple nuclear fission is comprised determining that from respective primary importance to the migration of the respective second position along the first dimension Fuel subassembly selected several along the first dimension from respective primary importance to the spiral of the respective second position Migrate.
90. methods as described in provision 51, wherein determine the selected several of multiple fission fuel subassembly Multiple nuclear fission is comprised determining that from respective primary importance to the migration of the respective second position along the first dimension Selected several axial translation of fuel subassembly.
91. methods as described in provision 51, wherein determine the desired shape of nuclear fission row ripple burnfront Comprise determining that the approximately spherical of nuclear fission row ripple burnfront.
92. methods as described in provision 51, wherein determine the desired shape of nuclear fission row ripple burnfront Comprise determining that the continuous bend surface configuration of nuclear fission row ripple burnfront.
93. methods as described in provision 51, wherein the desired shape of nuclear fission row ripple burnfront is to enclose The most rotational symmetric around the second dimension.
94. methods as described in provision 51, wherein the desired shape of nuclear fission row ripple burnfront has Substantially n fold rotational symmetry around the second dimension.
95. methods as described in provision 51, the wherein desired shape right and wrong of nuclear fission row ripple burnfront Symmetrical.
96. methods as described in provision 95, wherein the desired shape of nuclear fission row ripple burnfront is to enclose Rotationally asymmetric around the second dimension.
97. 1 kinds of systems, comprise:
First circuit, is configured to the nuclear fission row ripple burnfront for propagating along the first and second dimensions, Retrain according to the dimension of selected group in multiple fission fuel subassemblies and determine nuclear fission along the second dimension The desired shape of row ripple burnfront；And
Second circuit, is configured in the way of the desired shape of response determine multiple fission fuel subassembly Selected several along the first dimension from respective primary importance to the migration of the respective second position.
98. systems as described in provision 97, wherein said second circuit is further configured to determine that core splits Become the existing shape of row ripple burnfront.
99. systems as described in provision 97, wherein said second circuit is further configured to set up institute The mode of desirable shape, determine multiple fission fuel subassembly selected several along the first dimension from respectively From primary importance to the migration of the respective second position.
100. systems as described in provision 97, wherein said second circuit is further configured to maintain The mode of desired shape, determine multiple fission fuel subassembly selected several along the first dimension from Each primary importance is to the migration of the respective second position.
101. systems as described in provision 97, wherein said second circuit is further configured to response The mode of desired shape, determines and migrates to the respective second position from respective primary importance along the first dimension Selected several time of multiple fission fuel subassemblies.
102. systems as described in provision 97, plurality of fission fuel subassembly is along the second dimension Elongation.
103. systems as described in provision 97, wherein the first dimension is almost grouped with multiple fission fuel The axis of elongation of part is orthogonal.
104. systems as described in provision 97, wherein the first dimension and the second dimension are the most mutually orthogonal.
105. systems as described in provision 97, wherein:
First dimension includes radial dimension；And
Second dimension includes axial dimension.
106. systems as described in provision 97, wherein:
First dimension includes axial dimension；And
Second dimension includes radial dimension.
107. systems as described in provision 97, wherein:
First dimension includes axial dimension；And
Second dimension includes transverse dimensions.
108. systems as described in provision 97, wherein:
First dimension includes transverse dimensions；And
Second dimension includes axial dimension.
109. systems as described in provision 97, wherein:
Primary importance includes outer position；And
The second position includes inner position.
110. systems as described in provision 109, wherein inner position and outer position based on reactor The geometry proximity of the core of core.
111. the system as described in provision 109, wherein inner position and outer position are based on neutron flux, Make the neutron flux on inner position more than the neutron flux on outer position.
112. systems as described in provision 109, wherein inner position and outer position are based on reactivity, make Obtain the k on inner positioneffectiveMore than the k on outer positioneffective。
113. systems as described in provision 97, wherein:
Primary importance includes inner position；And
The second position includes outer position.
114. systems as described in provision 113, wherein inner position and outer position based on reactor The geometry proximity of the core of core.
115. systems as described in provision 113, wherein inner position and outer position are based on neutron flux, Make the neutron flux on inner position more than the neutron flux on outer position.
116. systems as described in provision 113, wherein inner position and outer position are based on reactivity, make Obtain the k on inner positioneffectiveMore than the k on outer positioneffective。
117. systems as described in provision 97, wherein primary importance and the second position are along at the first dimension On the opposite side of reference value.
118. the system as described in provision 97, wherein primary importance and the second position include substantially equalizing At least one attribute.
119. systems as described in provision 118, at least one of which attribute include with in reactor core The geometry proximity in heart region.
120. systems as described in provision 118, at least one of which attribute includes neutron flux.
121. systems as described in provision 118, at least one of which attribute includes reactivity.
122. systems as described in provision 97, wherein said second circuit is further configured to determine many Selected several rotation of at least one of individual fission fuel subassembly.
123. systems as described in provision 97, wherein said second circuit is further configured to determine many Overturning of selected several at least one of individual fission fuel subassembly.
124. systems as described in provision 97, wherein the dimension constraint of selected group includes along the second dimension Predetermined maximal distance.
125. systems as described in provision 97, wherein the dimension constraint of selected group is at least one burning battle array The function of face criterion.
126. systems as described in provision 125, wherein burnfront criterion includes neutron flux.
127. systems as described in provision 126, wherein by neutron flux and multiple fission fuel subassemblies Selected several at least one be associated.
128. systems as described in provision 125, wherein burnfront criterion includes neutron fluence.
129. the system as described in provision 128, wherein by neutron fluence and multiple fission fuel subassemblies Selected several at least one be associated.
130. systems as described in provision 125, wherein burnfront criterion includes burnup.
131. systems as described in provision 130, wherein by the institute of burnup Yu multiple fission fuel subassemblies Several at least one is selected to be associated.
132. systems as described in provision 125, wherein burnfront criterion includes that multiple fission fuel divides At least one selected several interior burnfront position of assembly.
133. systems as described in provision 97, wherein said second circuit is further configured to determine many Individual fission fuel subassembly selected several along the first dimension from respective primary importance to respective second The radial migration put.
134. systems as described in provision 97, wherein said second circuit is further configured to determine many Individual fission fuel subassembly selected several along the first dimension from respective primary importance to respective second The spiral put migrates.
135. systems as described in provision 97, wherein said second circuit is further configured to determine many Selected several axial translation of individual fission fuel subassembly.
136. systems as described in provision 97, wherein said first circuit is further configured to determine core Fission row ripple burnfront approximately spherical.
137. systems as described in provision 97, wherein said first circuit is further configured to determine core The continuous bend surface configuration of fission row ripple burnfront.
138. systems as described in provision 97, wherein the desired shape of nuclear fission row ripple burnfront is The most rotational symmetric around the second dimension.
139. systems as described in provision 97, the wherein desired shape tool of nuclear fission row ripple burnfront There is the substantially n fold rotational symmetry around the second dimension.
140. systems as described in provision 97, wherein the desired shape of nuclear fission row ripple burnfront is Asymmetrical.
141. systems as described in provision 140, wherein the desired shape of nuclear fission row ripple burnfront is Rotationally asymmetric around the second dimension.
142. 1 kinds of computer software program products, comprise:
First computer-readable medium software program code, is configured to for passing along the first and second dimensions The nuclear fission row ripple burnfront broadcast, in multiple fission fuel subassemblies according to selected group dimension about Bundle, along the second dimension, determines the desired shape of nuclear fission row ripple burnfront；And
Second computer computer-readable recording medium software program code, is configured in the way of the desired shape of response, Determine multiple fission fuel subassembly selected several along the first dimension from respective primary importance to each The migration of the second position.
143. computer software program products as described in provision 142, wherein said second computer is readable Medium software program code is further configured to determine the existing shape of nuclear fission row ripple burnfront.
144. computer software program products as described in provision 142, wherein said second computer is readable Medium software program code is further configured to, in the way of setting up desired shape, determine that multiple core splits Become fuel subassembly selected several along the first dimension from respective primary importance moving to the respective second position Move.
145. computer software program products as described in provision 142, wherein said second computer is readable Medium software program code is further configured to, in the way of maintaining desired shape, determine that multiple core splits Become fuel subassembly selected several along the first dimension from respective primary importance moving to the respective second position Move.
146. computer software program products as described in provision 142, wherein said second computer is readable Medium software program code is further configured to, in the way of the desired shape of response, determine along first Dimension migrates selected by multiple fission fuel subassemblies several from respective primary importance to the respective second position Time.
147. computer software program products as described in provision 142, plurality of fission fuel is grouped Part extends along the second dimension.
148. computer software program products as described in provision 142, wherein the first dimension is almost with multiple The axis of elongation of fission fuel subassembly is orthogonal.
149. computer software program products as described in provision 142, wherein the first dimension and the second dimension The most mutually orthogonal.
150. computer software program products as described in provision 142, wherein:
First dimension includes radial dimension；And
Second dimension includes axial dimension.
151. computer software program products as described in provision 142, wherein:
First dimension includes axial dimension；And
Second dimension includes radial dimension.
152. computer software program products as described in provision 142, wherein:
First dimension includes axial dimension；And
Second dimension includes transverse dimensions.
153. computer software program products as described in provision 142, wherein:
First dimension includes transverse dimensions；And
Second dimension includes axial dimension.
154. computer software program products as described in provision 142, wherein:
Primary importance includes outer position；And
The second position includes inner position.
155. computer software program products as described in provision 154, wherein inner position and outer position Based on the geometry proximity with the core of reactor core.
156. computer software program products as described in provision 154, wherein inner position and outer position Based on neutron flux so that the neutron flux on inner position is more than the neutron flux on outer position.
157. computer software program products as described in provision 154, wherein inner position and outer position Based on reactivity so that the k on inner positioneffectiveMore than the k on outer positioneffective。
158. computer software program products as described in provision 142, wherein:
Primary importance includes inner position；And
The second position includes outer position.
159. computer software program products as described in provision 158, wherein inner position and outer position Based on the geometry proximity with the core of reactor core.
160. computer software program products as described in provision 158, wherein inner position and outer position Based on neutron flux so that the neutron flux on inner position is more than the neutron flux on outer position.
161. computer software program products as described in provision 158, wherein inner position and outer position Based on reactivity so that the k on inner positioneffectiveMore than the k on outer positioneffective。
162. computer software program products as described in provision 142, wherein primary importance and the second position It is on the opposite side of reference value along the first dimension.
163. computer software program products as described in provision 142, wherein primary importance and the second position Including at least one attribute substantially equalized.
164. computer software program products as described in provision 163, at least one of which attribute include with The geometry proximity of the central area of reactor core.
165. computer software program products as described in provision 163, during at least one of which attribute includes Sub-flux.
166. computer software program products as described in provision 163, at least one of which attribute includes instead Ying Xing.
167. computer software program products as described in provision 142, wherein said second computer is readable Medium software program code is further configured to determine the selected several of multiple fission fuel subassembly The rotation of at least one.
168. computer software program products as described in provision 142, wherein said second computer is readable Medium software program code is further configured to determine the selected several of multiple fission fuel subassembly Overturning of at least one.
169. computer software program products as described in provision 142, wherein the dimension constraint bag of selected group Include the predetermined maximal distance along the second dimension.
170. computer software program products as described in provision 142, wherein the dimension constraint of selected group is The function of at least one burnfront criterion.
171. computer software program products as described in provision 170, during wherein burnfront criterion includes Sub-flux.
172. computer software program products as described in provision 171, wherein by neutron flux and multiple cores Selected several at least one of fission fuel subassembly is associated.
173. computer software program products as described in provision 170, during wherein burnfront criterion includes Sub-fluence.
174. computer software program products as described in provision 173, wherein by neutron fluence and multiple cores Selected several at least one of fission fuel subassembly is associated.
175. computer software program products as described in provision 170, wherein burnfront criterion includes combustion Consumption.
176. computer software program products as described in provision 175, wherein by burnup and multiple nuclear fissions Selected several at least one of fuel subassembly is associated.
177. computer software program products as described in provision 170, wherein burnfront criterion includes many At least one selected several interior burnfront position of individual fission fuel subassembly.
178. computer software program products as described in provision 142, wherein said second computer is readable Medium software program code includes: the 3rd computer-readable medium software program code, is configured to determine many Individual fission fuel subassembly selected several along the first dimension from respective primary importance to respective second The radial migration put.
179. computer software program products as described in provision 142, wherein said second computer is readable Medium software program code includes: the 4th computer-readable medium software program code, is configured to determine many Individual fission fuel subassembly selected several along the first dimension from respective primary importance to respective second The spiral put migrates.
180. computer software program products as described in provision 142, wherein said second computer is readable Medium software program code includes: the 5th computer-readable medium software program code, is configured to determine many Selected several axial translation of individual fission fuel subassembly.
181. computer software program products as described in provision 142, wherein said first computer-readable Medium software program code includes: the 7th computer-readable medium software program code, is configured to determine core Fission row ripple burnfront approximately spherical.
182. computer software program products as described in provision 142, wherein said first computer-readable Medium software program code includes: the 8th computer-readable medium software program code, is configured to determine core The continuous bend surface configuration of fission row ripple burnfront.
183. computer software program products as described in provision 142, wherein nuclear fission row ripple burnfront Desired shape to be around the second dimension the most rotational symmetric.
184. computer software program products as described in provision 142, wherein nuclear fission row ripple burnfront Desired shape there is the substantially n fold rotational symmetry around the second dimension.
185. computer software program products as described in provision 142, wherein nuclear fission row ripple burnfront Desired shape be asymmetrical.
186. computer software program products as described in provision 185, wherein nuclear fission row ripple burnfront Desired shape to be around the second dimension rotationally asymmetric.
187. 1 kinds of systems, comprise:
First circuit, is configured to the nuclear fission row ripple burnfront for propagating along the first and second dimensions, Retrain according to the dimension of selected group in multiple fission fuel subassemblies and determine nuclear fission along the second dimension The desired shape of row ripple burnfront；
Second circuit, is configured in the way of the desired shape of response determine multiple fission fuel subassembly Selected several along the first dimension from respective primary importance to the migration of the respective second position；And
Subassembly, is configured to respond to described second circuit and migrates the selected several of multiple fission fuel subassemblies Individual.
188. systems as described in provision 187, wherein said second circuit is further configured to determine core The existing shape of fission row ripple burnfront.
189. systems as described in provision 187, wherein said second circuit is further configured to set up The mode of desired shape, determine multiple fission fuel subassembly selected several along the first dimension from Each primary importance is to the migration of the respective second position.
190. systems as described in provision 187, wherein said second circuit is further configured to；To maintain The mode of desired shape, determine multiple fission fuel subassembly selected several along the first dimension from Each primary importance is to the migration of the respective second position.
191. systems as described in provision 187, wherein said second circuit is further configured to response The mode of desired shape, determines and migrates to the respective second position from respective primary importance along the first dimension Selected several time of multiple fission fuel subassemblies.
192. systems as described in provision 187, plurality of fission fuel subassembly is along the second dimension Elongation.
193. systems as described in provision 187, wherein the first dimension is almost grouped with multiple fission fuel The axis of elongation of part is orthogonal.
194. systems as described in provision 187, wherein the first dimension and the second dimension are the most mutually orthogonal.
195. systems as described in provision 187, wherein:
First dimension includes radial dimension；And
Second dimension includes axial dimension.
196. systems as described in provision 187, wherein:
First dimension includes axial dimension；And
Second dimension includes radial dimension.
197. systems as described in provision 187, wherein:
First dimension includes axial dimension；And
Second dimension includes transverse dimensions.
198. systems as described in provision 187, wherein:
First dimension includes transverse dimensions；And
Second dimension includes axial dimension.
199. systems as described in provision 187, wherein:
Primary importance includes outer position；And
The second position includes inner position.
200. systems as described in provision 199, wherein inner position and outer position based on reactor The geometry proximity of the core of core.
201. systems as described in provision 199, wherein inner position and outer position are based on neutron flux, Make the neutron flux on inner position more than the neutron flux on outer position.
202. systems as described in provision 199, wherein inner position and outer position are based on reactivity, make Obtain the k on inner positioneffectiveMore than the k on outer positioneffective。
203. systems as described in provision 187, wherein:
Primary importance includes inner position；And
The second position includes outer position.
204. systems as described in provision 203, wherein inner position and outer position based on reactor The geometry proximity of the core of core.
205. systems as described in provision 203, wherein inner position and outer position are based on neutron flux, Make the neutron flux on inner position more than the neutron flux on outer position.
206. systems as described in provision 203, wherein inner position and outer position are based on reactivity, make Obtain the k on inner positioneffectiveMore than the k on outer positioneffective。
207. systems as described in provision 187, wherein primary importance and the second position are along at the first dimension On the opposite side of reference value.
208. systems as described in provision 187, wherein primary importance and the second position include substantially equalizing At least one attribute.
209. systems as described in provision 208, at least one of which attribute include with in reactor core The geometry proximity in heart region.
210. systems as described in provision 208, at least one of which attribute includes neutron flux.
211. systems as described in provision 208, at least one of which attribute includes reactivity.
212. systems as described in provision 187, wherein said second circuit is further configured to determine many Selected several rotation of at least one of individual fission fuel subassembly.
213. systems as described in provision 187, wherein said second circuit is further configured to；Determine many Overturning of selected several at least one of individual fission fuel subassembly.
214. systems as described in provision 187, wherein said subassembly includes nuclear fuel management device.
215. systems as described in provision 187, wherein said subassembly is further configured to from respective One position is to several selected by respective second position radial migration multiple fission fuel subassembly.
216. systems as described in provision 187, wherein said subassembly is further configured to from respective One position migrates selected by multiple fission fuel subassemblies several to respective second position spiral.
217. systems as described in provision 187, wherein said subassembly is further configured to axial translation Multiple fission fuel subassemblies selected several.
218. systems as described in provision 187, wherein said subassembly is further configured to rotate multiple Fission fuel subassembly selected several.
219. systems as described in provision 187, wherein said subassembly is further configured to reverse multiple Fission fuel subassembly selected several.
220. 1 kinds of nuclear fission row ripple reactors, comprise:
Nuclear fission row ripple reactor core；
It is received in the multiple fission fuel subassemblies in described nuclear fission row ripple reactor core, described many Each of individual fission fuel subassembly is configured to make nuclear fission row ripple burnfront wherein along One and second dimension propagate；
First circuit, is configured in multiple fission fuel subassemblies retrain edge according to the dimension of selected group The second dimension, determine the desired shape of nuclear fission row ripple burnfront；
Second circuit, is configured to, in the way of the desired shape of response, determine that multiple fission fuel is grouped Part selected several along the first dimension from respective primary importance to the migration of the respective second position；And
Subassembly, is configured to respond to described second circuit and migrates the selected several of multiple fission fuel subassemblies Individual.
221. reactors as described in provision 220, wherein said second circuit is further configured to determine The existing shape of nuclear fission row ripple burnfront.
222. reactors as described in provision 220, wherein said second circuit is further configured to build The mode of vertical desired shape, determines the selected several along the first dimension of multiple fission fuel subassembly From respective primary importance to the migration of the respective second position.
223. reactors as described in provision 220, wherein said second circuit is further configured to dimension Hold the mode of desired shape, determine the selected several along the first dimension of multiple fission fuel subassembly From respective primary importance to the migration of the respective second position.
224. reactors as described in provision 220, wherein said second circuit is further configured to sound Desired by should, the mode of shape, determines and moves to the respective second position from respective primary importance along the first dimension Move selected several time of multiple fission fuel subassembly.
225. reactors as described in provision 220, plurality of fission fuel subassembly is along the second dimension Degree elongation.
226. reactors as described in provision 220, wherein the first dimension is almost divided with multiple fission fuel The axis of elongation of assembly is orthogonal.
227. reactors as described in provision 220, wherein the first dimension and the second dimension are the most mutually orthogonal.
228. reactors as described in provision 220, wherein:
First dimension includes radial dimension；And
Second dimension includes axial dimension.
229. reactors as described in provision 220, wherein:
First dimension includes axial dimension；And
Second dimension includes radial dimension.
230. reactors as described in provision 220, wherein:
First dimension includes axial dimension；And
Second dimension includes transverse dimensions.
231. reactors as described in provision 220, wherein:
First dimension includes transverse dimensions；And
Second dimension includes axial dimension.
232. reactors as described in provision 220, wherein:
Primary importance includes outer position；And
The second position includes inner position.
233. reactors as described in provision 232, wherein inner position and outer position based on reactor The geometry proximity of the core of reactor core.
234. reactors as described in provision 232, wherein inner position and outer position are based on neutron flux, Make the neutron flux on inner position more than the neutron flux on outer position.
235. reactors as described in provision 232, wherein inner position and outer position are based on reactivity, Make the k on inner positioneffectiveMore than the k on outer positioneffective。
236. reactors as described in provision 220, wherein:
Primary importance includes inner position；And
The second position includes outer position.
237. reactors as described in provision 236, wherein inner position and outer position based on reactor The geometry proximity of the core of reactor core.
238. reactors as described in provision 236, wherein inner position and outer position are based on neutron flux, Make the neutron flux on inner position more than the neutron flux on outer position.
239. reactors as described in provision 236, wherein inner position and outer position are based on reactivity, Make the k on inner positioneffectiveMore than the k on outer positioneffective。
240. reactors as described in provision 220, wherein primary importance and the second position are along the first dimension It is on the opposite side of reference value.
241. reactors as described in provision 220, wherein primary importance and the second position include substantially equalizing At least one attribute.
242. reactors as described in provision 241, at least one of which attribute includes and reactor core The geometry proximity of central area.
243. reactors as described in provision 241, at least one of which attribute includes neutron flux.
244. reactors as described in provision 241, at least one of which attribute includes reactivity.
245. reactors as described in provision 220, wherein said second circuit is further configured to determine Selected several rotation of at least one of multiple fission fuel subassemblies.
246. reactors as described in provision 220, wherein said second circuit is further configured to determine Overturning of selected several at least one of multiple fission fuel subassemblies.
247. reactors as described in provision 220, wherein the dimension constraint of selected group includes along the second dimension The predetermined maximal distance of degree.
248. reactors as described in provision 220, wherein the dimension constraint of selected group is at least one burning The function of front criterion.
249. reactors as described in provision 220, wherein burnfront criterion includes neutron flux.
250. reactors as described in provision 249, are wherein grouped neutron flux with multiple fission fuel Selected several at least one of part is associated.
251. reactors as described in provision 248, wherein burnfront criterion includes neutron fluence.
252. reactors as described in provision 251, are wherein grouped neutron fluence with multiple fission fuel Selected several at least one of part is associated.
253. reactors as described in provision 248, wherein burnfront criterion includes burnup.
254. reactors as described in provision 253, wherein by burnup and multiple fission fuel subassemblies Selected several at least one is associated.
255. reactors as described in provision 248, wherein burnfront criterion includes multiple fission fuel At least one selected several interior burnfront position of subassembly.
256. reactors as described in provision 220, wherein said second circuit is further configured to determine Multiple fission fuel subassemblies selected several along the first dimension from respective primary importance to respective second The radial migration of position.
257. reactors as described in provision 220, wherein said second circuit is further configured to determine Multiple fission fuel subassemblies selected several along the first dimension from respective primary importance to respective second The spiral of position migrates.
258. reactors as described in provision 220, wherein said second circuit is further configured to determine many Selected several axial translation of individual fission fuel subassembly.
259. reactors as described in provision 220, wherein said first circuit is further configured to determine Nuclear fission row ripple burnfront approximately spherical.
260. reactors as described in provision 220, wherein said first circuit is further configured to determine The continuous bend surface configuration of nuclear fission row ripple burnfront.
261. reactors as described in provision 220, the wherein desired shape of nuclear fission row ripple burnfront It is around the second dimension the most rotational symmetric.
262. reactors as described in provision 220, the wherein desired shape of nuclear fission row ripple burnfront There is the substantially n fold rotational symmetry around the second dimension.
263. reactors as described in provision 220, the wherein desired shape of nuclear fission row ripple burnfront It is asymmetrical.
264. reactors as described in provision 220, the wherein desired shape of nuclear fission row ripple burnfront It is around the second dimension rotationally asymmetric.
265. reactors as described in provision 220, wherein said subassembly includes nuclear fuel management device.
266. reactors as described in provision 220, wherein said subassembly is further configured to from each Primary importance is to several selected by respective second position radial migration multiple fission fuel subassembly.
267. reactors as described in provision 220, wherein said subassembly is further configured to from each Primary importance migrates selected by multiple fission fuel subassemblies several to respective second position spiral.
268. reactors as described in provision 220, wherein said subassembly is further configured to the most flat Move the selected several of multiple fission fuel subassembly.
269. reactors as described in provision 220, it is many that wherein said subassembly is further configured to rotation Individual fission fuel subassembly selected several.
270. reactors as described in provision 220, wherein said subassembly is further configured to；Reverse many Individual fission fuel subassembly selected several.
271. 1 kinds of methods operating nuclear fission row ripple reactor, described method comprises:
By at least one fission fuel assemblies, the primary importance from nuclear fission row ripple reactor core to Move outside the second position moved on in nuclear fission row ripple reactor core.
272. methods as described in provision 271, comprise further from second position inward migration at least one Fission fuel assemblies.
273. methods as described in provision 271, wherein primary importance and the second position based on reactor The geometry proximity of the core of core.
274. methods as described in provision 272, wherein primary importance and the second position are based on neutron flux, Make the neutron flux on inner position more than the neutron flux on outer position.
275. methods as described in provision 271, wherein primary importance and the second position are based on reactivity, make Obtain the k on inner positioneffectiveMore than the k on outer positioneffective。
276. 1 kinds of methods operating nuclear fission row ripple reactor, described method comprises:
Determine that at least one fission fuel assemblies is along a first direction from nuclear fission row ripple reactor core Primary importance to the migration of the second position in nuclear fission row ripple reactor core, the second position is different from Primary importance；And
Determine at least one fission fuel assemblies along second direction from the migration of the second position, second party To being different from first direction.
277. methods as described in provision 276, wherein:
First direction is outside；And
Second direction is inside.
278. methods as described in provision 277, wherein primary importance and the second position based on reactor The geometry proximity of the core of core.
279. methods as described in provision 277, wherein primary importance and the second position are based on neutron flux, Make the neutron flux on inner position more than the neutron flux on outer position.
280. methods as described in provision 277, wherein primary importance and the second position are based on reactivity, make Obtain the k on inner positioneffectiveMore than the k on outer positioneffective。
281. methods as described in provision 276, wherein:
First direction is inside；And
Second direction is outside.
282. methods as described in provision 281, wherein the second position and primary importance based on reactor The geometry proximity of the core of core.
283. methods as described in provision 281, wherein the second position and primary importance are based on neutron flux, Make the neutron flux on inner position more than the neutron flux on outer position.
284. the method as described in provision 281, wherein the second position and primary importance are based on reactivity, make Obtain the k on inner positioneffectiveMore than the k on outer positioneffective。
285. 1 kinds of methods operating nuclear fission row ripple reactor, described method comprises:
By at least one fission fuel assemblies along a first direction from nuclear fission row ripple reactor core Primary importance moves to the second position in nuclear fission row ripple reactor core, and the second position is different from first Position；And
Determine at least one fission fuel assemblies along second direction from the migration of the second position, second party To being different from first direction.
286. methods as described in provision 285, wherein:
First direction is outside；And
Second direction is inside.
287. methods as described in provision 286, wherein primary importance and the second position based on reactor The geometry proximity of the core of core.
288. methods as described in provision 286, wherein primary importance and the second position are based on neutron flux, Make the neutron flux on inner position more than the neutron flux on outer position.
289. methods as described in provision 286, wherein primary importance and the second position are based on reactivity, make Obtain the k on inner positioneffectiveMore than the k on outer positioneffective。
290. methods as described in provision 286, wherein:
First direction is inside；And
Second direction is outside.
291. methods as described in provision 290, wherein the second position and primary importance based on reactor The geometry proximity of the core of core.
292. methods as described in provision 290, wherein the second position and primary importance are based on neutron flux, Make the neutron flux on inner position more than the neutron flux on outer position.
293. methods as described in provision 290, wherein the second position and primary importance are based on reactivity, make Obtain the k on inner positioneffectiveMore than the k on outer positioneffective。
294. 1 kinds of methods operating nuclear fission row ripple reactor, described method comprises:
By at least one fission fuel assemblies along a first direction from nuclear fission row ripple reactor core Primary importance moves to the second position in nuclear fission row ripple reactor core, and the second position is different from first Position；And
Migrating at least one fission fuel assemblies along second direction from the second position, second direction is different In first direction.
295. methods as described in provision 294, wherein:
First direction is outside；And
Second direction is inside.
296. methods as described in provision 295, wherein primary importance and the second position based on reactor The geometry proximity of the core of core.
297. methods as described in provision 295, wherein primary importance and the second position are based on neutron flux, Make the neutron flux on inner position more than the neutron flux on outer position.
298. methods as described in provision 295, wherein primary importance and the second position are based on reactivity, make Obtain the k on inner positioneffectiveMore than the k on outer positioneffective。
299. methods as described in provision 294, wherein:
First direction is inside；And
Second direction is outside.
300. methods as described in provision 299, wherein the second position and primary importance based on reactor The geometry proximity of the core of core.
301. methods as described in provision 299, wherein the second position and primary importance are based on neutron flux, Make the neutron flux on inner position more than the neutron flux on outer position.
302. methods as described in provision 299, wherein the second position and primary importance are based on reactivity, make Obtain the k on inner positioneffectiveMore than the k on outer positioneffective。
303. 1 kinds of methods operating nuclear fission row ripple reactor, described method comprises:
Select predetermined burn up level；And
All to reach the burnup water equal to predetermined burn up level in nearly all multiple fission fuel assemblies Flat mode, determines selected several the moving of multiple fission fuel assemblies in fission-type reactor reactor core Move.
304. methods as described in provision 303, comprise further:
In the way of responding determined migration, migrate the multiple fission fuel in fission-type reactor reactor core Assembly selected several
305. methods as described in provision 304, comprise further: when burn up level is equal to predetermined burnup water At ordinary times, determine each selected several of multiple fission fuel assemblies are removed.
306. methods as described in provision 305, comprise: remove determined by response further, remove many Individual fission fuel assemblies selected several.
Although having been disclosed for various aspects and embodiment herein, but other side and embodiment being for ability It is apparent from for the those of ordinary skill in territory.Various aspects disclosed herein and embodiment are simply The purpose that illustrates rather than be intended to limit, true scope and spirit are pointed out by claims below.

Claims (41)

1. operating a device for nuclear fission row ripple reactor, described device comprises:
Circuit, in the multiple fission fuel subassemblies in the reactor core of nuclear fission row ripple reactor, Nuclear fission row ripple burnfront is made to propagate along the first and second dimensions；And
Subassembly, along the first dimension from respective primary importance to the respective second position multiple core of controlled migration Fission fuel subassembly selected several, so that limiting nuclear fission according to dimension constraint along the second dimension The shape of row ripple burnfront,
Wherein dimension constraint includes the function of at least one burnfront criterion,
Wherein the first dimension and the second dimension are the most mutually orthogonal.
2. device as claimed in claim 1, plurality of fission fuel subassembly is along the second dimension Elongation.
3. device as claimed in claim 1, wherein the first dimension is almost grouped with multiple fission fuel The axis of elongation of part is orthogonal.
4. device as claimed in claim 1, wherein:
First dimension includes the radial dimension of fission fuel subassembly；And
Second dimension includes the axial dimension of fission fuel subassembly.
5. device as claimed in claim 1, wherein:
First dimension includes the axial dimension of fission fuel subassembly；And
Second dimension includes the radial dimension of fission fuel subassembly.
6. device as claimed in claim 1, wherein:
First dimension includes the axial dimension of fission fuel subassembly；And
Second dimension includes the transverse dimensions of fission fuel subassembly.
7. device as claimed in claim 1, wherein:
First dimension includes the transverse dimensions of fission fuel subassembly；And
Second dimension includes the axial dimension of fission fuel subassembly.
8. device as claimed in claim 1, wherein:
Primary importance includes the outer position of reactor core；And
The second position includes the inner position of reactor core.
9. such as claim 8, the device described in any one of 10, wherein inner position and outer position Based on from following at least one attribute selected: with the geometry proximity of the core of reactor core； Neutron flux so that the neutron flux on inner position is more than the neutron flux on outer position；And it is anti- Ying Xing so that the k on inner positioneffectiveMore than the k on outer positioneffective。
10. device as claimed in claim 1, wherein:
Primary importance includes the inner position of reactor core；And
The second position includes the outer position of reactor core.
11. devices as claimed in claim 1, wherein primary importance and the second position include substantially equalizing At least one attribute.
12. devices as claimed in claim 11, at least one of which attribute includes being selected from and reactor The attribute of geometry proximity, neutron flux and the reactivity of the central area of core.
13. devices as claimed in claim 1, wherein said subassembly along the first dimension from respective One position to the respective second position, selected several the including of controlled migration multiple fission fuel subassembly: Rotate selected several at least one of multiple fission fuel subassembly.
14. devices as claimed in claim 1, wherein said subassembly along the first dimension from respective One position to the respective second position, selected several the including of controlled migration multiple fission fuel subassembly: Selected several at least one of reverse multiple fission fuel subassemblies.
15. devices as claimed in claim 1, wherein dimension constraint also include along the second dimension pre- Determine ultimate range.
16. devices as claimed in claim 1, wherein burnfront criterion includes neutron flux.
17. devices as claimed in claim 16, are wherein grouped neutron flux with multiple fission fuel Selected several at least one of part is associated.
18. devices as claimed in claim 1, wherein burnfront criterion includes neutron fluence.
19. devices as claimed in claim 18, are wherein grouped neutron fluence with multiple fission fuel Selected several at least one of part is associated.
20. devices as claimed in claim 1, wherein burnfront criterion includes burnup.
21. devices as claimed in claim 20, wherein by burnup and multiple fission fuel subassemblies Selected several at least one is associated.
22. devices as claimed in claim 1, wherein burnfront criterion includes multiple fission fuel At least one selected several interior burnfront position of subassembly.
23. devices as claimed in claim 1, wherein said subassembly along the first dimension from respective One position to the respective second position, selected several the including of controlled migration multiple fission fuel subassembly: Along the first dimension from respective primary importance to the respective second position, the multiple nuclear fission of the most controlled migration Fuel subassembly selected several.
24. devices as claimed in claim 1, wherein said subassembly along the first dimension from respective One position to the respective second position, selected several the including of controlled migration multiple fission fuel subassembly: Along the first dimension from respective primary importance to the respective second position, the multiple nuclear fission of the most controlled migration Fuel subassembly selected several.
25. devices as claimed in claim 1, wherein said subassembly along the first dimension from respective One position to the respective second position, selected several the including of controlled migration multiple fission fuel subassembly: Along the first dimension from respective primary importance to the respective second position, the multiple nuclear fission of the most controlled migration Fuel subassembly selected several.
26. device as claimed in claim 1, the wherein shapes of the restriction of nuclear fission row ripple burnfront Including from the following shape selected: approximately spherical；The shape being consistent with selected continuous bend surface；Around The second the most rotational symmetric shape of dimension；And have around the second dimension substantially n fold rotational symmetry Shape.
27. devices as claimed in claim 1, wherein nuclear fission row ripple burnfront is along the second dimension Shape be asymmetrical.
28. devices as claimed in claim 27, wherein the shape of nuclear fission row ripple burnfront is around Second dimension is rotationally asymmetric.
29. devices as claimed in claim 1, comprise multiple nuclear fission row ripple ignition module further, Its initiated core fission row ripple burnfront.
30. devices as claimed in claim 29, comprise described subassembly further along the first dimension From respective primary importance to the respective second position, controlled migration multiple fission fuel subassembly selected several Before individual, remove at least one of multiple nuclear fission row ripple ignition module.
31. devices as claimed in claim 30, wherein said subassembly along the first dimension from each Primary importance to the respective second position, controlled migration multiple fission fuel subassembly selected several before, At least one removing multiple nuclear fission row ripple ignition module includes: along the first dimension from respective first Position to the respective second position, controlled migration multiple fission fuel subassembly selected several before, from The second position removes at least one of multiple nuclear fission row ripple ignition module.
32. devices as claimed in claim 1, comprise described subassembly further and make nuclear fission row ripple anti- Should pile up and fire to the multiple nuclear fission of controlled migration of the respective second position from respective primary importance along the first dimension Material subassembly selected several before, become subcritical.
33. devices as claimed in claim 32, wherein said subassembly makes nuclear fission row ripple reactor become Become subcritical to include in neutron absorber material insertion reaction heap reactor core.
34. devices as claimed in claim 32, comprise further: described subassembly is along the first dimension Spend from respective primary importance to several selected by the controlled migration of the respective second position multiple fission fuel subassembly After individual, re-establish critical.
35. devices as claimed in claim 34, wherein re-establish critical including from reactor core Remove at least part of of neutron absorber material.
36. devices as claimed in claim 32, comprise further: described subassembly is along the first dimension Spend from respective primary importance to several selected by the controlled migration of the respective second position multiple fission fuel subassembly Before individual, close nuclear fission row ripple reactor.
37. devices as claimed in claim 36, comprise further: described subassembly is along the first dimension Spend from respective primary importance to several selected by the controlled migration of the respective second position multiple fission fuel subassembly After individual, restart nuclear fission row ripple reactor.
38. 1 kinds of devices operating fission-type reactor, described device comprises:
Circuit, selects predetermined burn up level；And
Subassembly, all to reach equal to predetermined burn up level in nearly all multiple fission fuel assemblies The mode of burn up level, determine the selected of multiple fission fuel assemblies in fission-type reactor reactor core Several migrations.
39. devices as claimed in claim 38, comprise further:
Described subassembly to respond in the way of determined migration, multiple in migration fission-type reactor reactor core Fission fuel assemblies selected several.
40. devices as claimed in claim 39, comprise further: described subassembly is when burn up level etc. When predetermined burn up level, determine the most selected several the removing of multiple fission fuel assemblies.
41. devices as claimed in claim 40, comprise further: determined by the response of described subassembly Remove, remove the selected several of multiple fission fuel assemblies.
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US12/657,735 US9786392B2 (en) 2009-11-06 2010-01-25 Methods and systems for migrating fuel assemblies in a nuclear fission reactor
US12/657,735 2010-01-25
US12/657,726 US9799416B2 (en) 2009-11-06 2010-01-25 Methods and systems for migrating fuel assemblies in a nuclear fission reactor
US12/657,726 2010-01-25
US12/657,725 US9922733B2 (en) 2009-11-06 2010-01-25 Methods and systems for migrating fuel assemblies in a nuclear fission reactor
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