CN102460594B - A nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system - Google Patents
A nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system Download PDFInfo
- Publication number
- CN102460594B CN102460594B CN201080027017.6A CN201080027017A CN102460594B CN 102460594 B CN102460594 B CN 102460594B CN 201080027017 A CN201080027017 A CN 201080027017A CN 102460594 B CN102460594 B CN 102460594B
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- Prior art keywords
- fission
- flow
- nuclear fission
- module
- subassembly
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/32—Control of nuclear reaction by varying flow of coolant through the core by adjusting the coolant or moderator temperature
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
-
- 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 refuelling, 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
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/322—Means to influence the coolant flow through or around the bundles
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Flow Control (AREA)
Abstract
A nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system. The flow control assembly is coupled to a nuclear fission module capable of producing a traveling burn wave at a location relative to the nuclear fission module. The flow control assembly controls flow of a fluid in response to the location relative to the nuclear fission module. The flow control assembly comprises a flow regulator subassembly configured to be operated according to an operating parameter associated with the nuclear fission module. In addition, the flow regulator subassembly is reconfigurable according to a predetermined input to the flow regulator subassembly. Moreover, the flow control assembly comprises a carriage subassembly coupled to the flow regulator subassembly for adjusting the flow regulator subassembly to vary fluid flow into the nuclear fission module.
Description
Cross
The application relate to following listed application (" related application ") and require to obtain from following listed application the earliest can with the rights and interests of live application day (such as, require the available priority dates the earliest of non-provisional, or require temporary patent application, and in any and all parents of related application, Zu Fudai, great grandfather's generation etc., apply for the rights and interests based on 35USC § 119 (e)).All themes of the application such as any and all parents, Zu Fudai, great grandfather's generation of related application and related application can not the degree inconsistent with theme herein be incorporated herein by reference with such theme.
related application
According to the non-legal requirements of U.S.Patent & Trademark Office (USPTO), the application forms submission on April 16th, 2009, invention people is Charles E.Ahlfeld, Roderick A.Hyde, Muriel Y.Ishikawa, David G.McAlees, Jon D McWhirter, Nathan P.Myhrvold, AshokOdedra, Clarence T.Tegreene, Thomas Allan Weaver, Charles Whitmer, VictoriaY.H.Wood, Lowell L.Wood, Jr. and George B.Zimmerman, it is " ANUCLEAR FISSION REACTOR, FLOW CONTROL ASSEMBLY, METHODSTHEREFOR AND A FLOW CONTROL ASSEMBLY SYSTEM (fission-type reactor with denomination of invention, flow control assembly, its method and flow control assembly system) " U.S. Patent application the 12/386th, the part continuation application of No. 495, the pending trial while that this application being current, or the while of giving current co-pending application with the application of the rights and interests of the applying date.
According to the non-legal requirements of U.S.Patent & Trademark Office (USPTO), the application forms submission on July 13rd, 2009, invention people is Charles E.Ahlfeld, Roderick A.Hyde, Muriel Y.Ishikawa, David G.McAlees, Jon D McWhirter, Nathan P.Myhrvold, AshokOdedra, Clarence T.Tegreene, Thomas Allan Weaver, Charles Whitmer, VictoriaY.H.Wood, Lowell L.Wood, Jr. and George B.Zimmerman, it is " ANUCLEAR FISSION REACTOR, FLOW CONTROL ASSEMBLY, METHODSTHEREFOR AND A FLOW CONTROL ASSEMBLY SYSTEM (fission-type reactor with denomination of invention, flow control assembly, its method and flow control assembly system) " U.S. Patent application the 12/460th, the part continuation application of No. 157, the pending trial while that this application being current, or the while of giving current co-pending application with the application of the rights and interests of the applying date.
According to the non-legal requirements of U.S.Patent & Trademark Office (USPTO), the application forms submission on July 13rd, 2009, invention people is Charles E.Ahlfeld, Roderick A.Hyde, Muriel Y.Ishikawa, David G.McAlees, Jon D McWhirter, Nathan P.Myhrvold, AshokOdedra, Clarence T.Tegreene, Thomas Allan Weaver, Charles Whitmer, VictoriaY.H.Wood, Lowell L.Wood, Jr. and George B.Zimmerman, it is " ANUCLEAR FISSION REACTOR, FLOW CONTROL ASSEMBLY, METHODSTHEREFOR AND A FLOW CONTROL ASSEMBLY SYSTEM (fission-type reactor with denomination of invention, flow control assembly, its method and flow control assembly system) " U.S. Patent application the 12/460th, the part continuation application of No. 160, the pending trial while that this application being current, or the while of giving current co-pending application with the application of the rights and interests of the applying date.
According to the non-legal requirements of U.S.Patent & Trademark Office (USPTO), the application forms submission on July 13rd, 2009, invention people is Charles E.Ahlfeld, Roderick A.Hyde, Muriel Y.Ishikawa, David G.McAlees, Jon D McWhirter, Nathan P.Myhrvold, AshokOdedra, Clarence T.Tegreene, Thomas Allan Weaver, Charles Whitmer, VictoriaY.H.Wood and Lowell L.Wood, Jr., be " A NUCLEAR FISSIONREACTOR with denomination of invention, FLOW CONTROL ASSEMBLY, METHODS THEREFOR AND AFLOW CONTROL ASSEMBLY SYSTEM (fission-type reactor, flow control assembly, its method and flow control assembly system) " U.S. Patent application the 12/460th, the part continuation application of No. 159, the pending trial while that this application being current, or the while of giving current co-pending application with the application of the rights and interests of the applying date.
U.S.Patent & Trademark Office (USPTO) has issued content and has been that the computer program of USPTO requires patent applicant to quote sequence number and instruction application is the bulletin of continuation application or part continuation application.Details refers to the article can found on http://www.uspto.gov/web/offices/com/sol/og/2003/week11/patbene .htm., Stephen G.Kunin, Benefit of Prior-FiledApplication, USPTO Official Gazette March 18,2003.The applicant's entity (hereinafter referred to as " applicant ") requires that the specific of the application of its right of priority is quoted being provided above as described in regulation.The applicant understands, and this regulation is clear and definite its specific quoting on language, does not need sequence number or any sign as " continuation " or " part continues " to carry out the right of priority of requirement U.S. Patent application.Although as described above, but the applicant understands, the computer program of USPTO has some data entry requirement, therefore the application is designated as the part continuation of its parent application as mentioned above by the applicant, but should explicitly point out, such appointment must not be understood as except the theme of its parent application, and whether the application comprises the annotation of any type of certain new theme and/or admit.
Technical field
The application relates generally to involve the process of induced nuclear reaction and realize the structure of such process, this structure comprises hole on entrance, outlet or cooling duct or fluid control device, particularly relates to fission-type reactor, flow control assembly, its method and flow control assembly system.
Background technology
As everyone knows, in the fission-type reactor run, the neutron of known energy is absorbed by the nucleic with thick atom quality.The compound nucleus produced resolves into the fission product and decay product that comprise two less atomic mass fission fragments.The nucleic that the known neutron by all energy stands such fission comprises uranium-233, uranium-235 and plutonium-239, and they are all fissilenuclides.Such as, kinetic energy is that the thermal neutron of 0.0253eV (electron-volt) can be used for making U-235 nuclear fission.Fission can not be brought out, except non-used kinetic energy is the fast neutron of at least 1MeV (million-electron-volt) as the thorium-232 and uranium-238 that can breed nucleic.The total kinetic energy discharged from each fission event is about 200MeV.This kinetic energy finally changes into heat.
In nuclear reactor, above-mentioned fissible and/or usually can leave in and define in the multiple tightly packed fuel assembly together of nuclear reactor by fertile material.Observe, heat accumulation may make so tightly packed fuel assembly together and other reactor component experience differential thermal expansion, causes the misalignment of reactor core components.Heat accumulation also may impel the fuel rod creep of the risk that can increase fuel rod swelling and fuel rod clad fracture during reactor operation.This may add the risk that fuel pellet may break and/or fuel rod may bend.Fuel pellet breaks and may prior to the fuel as fuel-involucrum mechanical interaction-involucrum fault mechanism, and cause fission gas to discharge.Fission gas release can produce higher than normal radiation level in reactor core.Fuel rod is bending may cause coolant flow channel to be blocked.
Do the trial enough cooling medium stream being supplied to fuel assembly for nuclear reactor.Issue and with denomination of invention be the United States Patent (USP) the 4th of " Device for Regulating the Flow ofa Fluid (regulating the equipment of the flow of fluid) " on March 19th, 1985 with the name of Jacky Rion, 505, No. 877 disclose the equipment comprised with a series of grids in the direction of fluid flow and alter stream.According to the patent of Rion, this equipment intends to be used in the direction regulating the cooling fluid circulated in the pedestal of liquid metal cooling nuclear reactor component.Being devoted to of this equipment, for given nominal flow rate and given downstream pressure, does not cause to constant pressure drop with not producing cavity.
Issuing with the name of the people such as Neil G.Heppenstall on November 19th, 1991 is the United States Patent (USP) the 5th of " Nuclear Fuel Assembly Coolant Control (control of nuclear fuel assembly cooling medium) " with denomination of invention, 066, in No. 453, disclose the another kind enough cooling medium stream being supplied to fuel assembly for nuclear reactor and attempt.The device that the position this patent disclose the device of the flow by the agent of nuclear fuel assembly controlled cooling model, this device comprises the variable restrictor that can be in fuel assembly, being in fuel assembly responds neutron irradiation in the mode causing self neutron to bring out to increase is connected with variable restrictor with by neutron irradiation responding device so that controlled cooling model agent is by the coupling arrangement of the flow of fuel assembly.Variable restrictor comprises many longitudinal directions and to align pipeline and have the blocking device that can be in some ducted type of tamper evidence arrays, and type of tamper evidence has different length, to open or close some pipelines gradually by coupling arrangement length travel blocking device.
Issuing with the name of John P.Church on March 30th, 1993 is the United States Patent (USP) the 5th of " NuclearReactor Flow Control Method and Apparatus (nuclear reactor flow control methods and device) " with denomination of invention, 198, in No. 185, disclose another trial enough cooling medium stream being supplied to fuel assembly for nuclear reactor.This patent seems to disclose the cooling medium flow point cloth not making flowing worsen at nominal conditions occurring to make flowing improve under event conditions.According to this patent, Universal casing shell surrounds fuel element.This Universal casing shell has the multiple holes allowing cooling medium pass through.Sleeve pipe ground is changed the quantity in the hole in sleeve shell and size one by one, to increase the quantity flowing to the cooling medium of reactor core center fuel, and is relatively reduced to the flow of peripheral fuel.In addition, according to this patent, the change quantity in hole and the size in hole can meet the certain power shape striding across reactor core.
Summary of the invention
According to an aspect of the present disclosure, provide a kind of fission-type reactor, it comprises nuclear fission module, is configured to have on the position relative to this nuclear fission module row ripple (travelingburn wave) that burns at least partially; And flow control assembly, be configured to be coupled and be configured to respond the flow being in and regulating fluid relative to the burning row ripple on the position of this nuclear fission module with this nuclear fission module.
According to another aspect of the present disclosure, provide a kind of fission-type reactor, it comprises heating fission fuel assemblies, is configured to relative to the position of this fission fuel assemblies having the row ripple of burning at least partially; And flow control assembly, be configured to be coupled with this fission fuel assemblies and the flow being in and regulating fluid stream relative to the burning row ripple on the position of this fission fuel assemblies can be responded.
According to another aspect of the present disclosure, provide a kind of flow control assembly with being expert in ripple fission-type reactor, it comprises flow regulation subassembly.
According to another aspect of the present disclosure, provide a kind of flow control assembly be used in fission-type reactor, it comprises flow regulation subassembly, and this flow regulation subassembly comprises first sleeve pipe with the first hole; Be configured to the second sleeve pipe in insertion first sleeve pipe, the second sleeve pipe has the second hole can aimed at the first hole, and the first sleeve pipe is configured to rotatable, to make the first hole aim at the second hole; And be configured to the balladeur train subassembly that is coupled with flow regulation subassembly.
According to another aspect of the present disclosure, provide a kind of with being expert in ripple fission-type reactor, be configured to the flow control assembly that is connected with fuel assembly, it comprises and is configured to the adjustable flow be arranged in fluid stream and regulates subassembly.
According to further aspect of the present disclosure, provide and be a kind ofly used in fission-type reactor, be configured to the flow control assembly that is connected with fuel assembly, it comprises the adjustable flow adjustment subassembly being configured to be arranged in fluid stream, and this adjustable flow regulates subassembly to comprise first sleeve pipe with the first hole; And the second sleeve pipe be configured in insertion first sleeve pipe, second sleeve pipe has the second hole, first hole can be aimed at the second hole gradually, thus along with aiming at the second hole gradually in the first hole, the fluid stream of variable number flows through the first hole and the second hole, first sleeve pipe is configured to can relative to the second sleeve pipe axial translation, to make the second hole aim at the first hole.
According to other aspect of the present disclosure, provide and be a kind ofly used in fission-type reactor, be configured to the flow control assembly that is connected with fuel assembly, it comprises adjustable flow and regulates subassembly; And regulate subassembly to be coupled to adjust the balladeur train subassembly that adjustable flow regulates subassembly with adjustable flow.
According to another aspect of the present disclosure, provide a kind ofly to be used in fission-type reactor, can with the selected flow control assembly be coupled being arranged to the multiple fission fuel assemblies be arranged in fission-type reactor, it comprises the adjustable flow adjustment subassembly that the flow of the fluid stream of selected of multiple fission fuel assemblies is flow through in adjustment, and this adjustable flow regulates subassembly to comprise the outer tube with multiple first holes; Insert the inner sleeve in outer tube, inner sleeve has multiple second hole, first hole can be aimed to define variable flow district with the second hole gradually, thus defines variable flow district along with the first hole and the second hole are aimed at gradually, and the fluid stream of variable number flows through the first hole and the second hole; And regulate subassembly to be coupled to adjust the balladeur train subassembly that adjustable flow regulates subassembly with adjustable flow.
According to further aspect of the present disclosure, provide a kind of method running fission-type reactor, it is included on the position relative to nuclear fission module and produces the row ripple that burns at least partially; And response is relative to the position of nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.
According to another aspect of the present disclosure, provide the method for a kind of assembling with the flow control assembly of being expert in ripple fission-type reactor, it comprises receives flow regulation subassembly.
According to another aspect of the present disclosure, provide the method for a kind of assembling with the flow control assembly of being expert in ripple fission-type reactor, it comprises receives balladeur train subassembly.
According to another aspect of the present disclosure, provide the method for a kind of assembling with the flow control assembly of being expert in ripple fission-type reactor, it comprises the first sleeve pipe received and have the first hole; Inserted by second sleeve pipe in the first sleeve pipe, the second sleeve pipe has the second hole can aimed at the first hole, and the first sleeve pipe is configured to rotatable, to become to aim at the second hole by the first hole axial translation; And balladeur train subassembly is coupled with flow regulation subassembly.
According to other aspect of the present disclosure, provide the flow control assembly system with being expert in ripple fission-type reactor, it comprises flow regulation subassembly.
According to another aspect of the present disclosure, provide the flow control assembly system be used in fission-type reactor, it comprises flow regulation subassembly, and this flow regulation subassembly comprises first sleeve pipe with the first hole; Be configured to the second sleeve pipe in insertion first sleeve pipe, the second sleeve pipe has the second hole can aimed at the first hole, and the first sleeve pipe is configured to rotatable, to become to aim at the second hole by the first hole axial translation; And be configured to the balladeur train subassembly that is coupled with flow regulation subassembly.
According to another aspect of the present disclosure, provide and be a kind ofly used in fission-type reactor, be configured to the flow control assembly system that is connected with fission fuel assemblies, it comprises and is configured to the adjustable flow be arranged in fluid stream and regulates subassembly.
According to another aspect of the present disclosure, provide a kind ofly to be used in fission-type reactor, can with the selected flow control assembly system be coupled of the multiple fission fuel assemblies be arranged in fission-type reactor, it comprises the adjustable flow adjustment subassembly that control flow check crosses the flow of the fluid stream of selected of multiple fission fuel assemblies, and this adjustable flow regulates subassembly to comprise the outer tube with multiple first holes; Insert the inner sleeve in outer tube, inner sleeve has multiple second hole, first hole can be aimed to define variable flow district with the second hole gradually, thus defines variable flow district along with the first hole and the second hole are aimed at gradually, and the fluid stream of variable number flows through the first hole and the second hole; And regulate subassembly to be coupled to adjust the balladeur train subassembly that adjustable flow regulates subassembly with adjustable flow.
A feature of the present disclosure is to provide the flow control assembly of the flow of the position control fluid that can respond combustion wave.
Another feature of the present disclosure is to provide the flow control assembly comprising flow regulation subassembly, this flow regulation subassembly comprises outer tube and inner sleeve, outer tube has the first hole and inner sleeve has the second hole can aimed at the first hole, thus along with aiming at the first hole in the second hole, the fluid stream of some flows through the first hole and the second hole.
Other feature of the present disclosure is to provide and is configured to be coupled with flow regulation subassembly to transmit and to configure the balladeur train subassembly of flow regulation subassembly.
Except above, of the present disclosure as the instruction of text (such as, claims and/or detailed description) and/or accompanying drawing in propose and describe other method various and/or equipment aspect.
Be a summary above, therefore may comprise the simplification of details, summarize, comprise and/or omit; Therefore, those skilled in the art will recognize that, this summary is exemplary, and intends anything but to carry out any restriction.Except above-mentioned exemplary aspect, embodiment and feature, by reference to accompanying drawing and following detailed description, further aspect, embodiment and feature will become obvious.
Accompanying drawing explanation
Although this instructions, to particularly point out and differently to state that claims of theme of the present disclosure are as conclusion, believes that the disclosure better can be understood from following detailed description done by reference to the accompanying drawings.In addition, by the similar or identical project of same-sign ordinary representation in different figures.
Fig. 1 is schematically showing of fission-type reactor;
Figure 1A belongs to the nuclear fuel assembly of fission-type reactor or the cross-sectional view of nuclear fission module;
Figure 1B is that the perspective of the nuclear fuel rod belonging to nuclear fission module and partial vertical section represent;
Fig. 2 is the cross-sectional view of the hexagonal configuration fission-type reactor reactor core with the multiple hexagonal configuration nuclear fission modules be arranged in wherein;
Fig. 3 is the cross-sectional view of the cylindrical shape reactor core with the multiple hexagonal configuration nuclear fission modules be arranged in wherein;
Fig. 4 is the cross-sectional view of parallelepiped-shaped reactor core, and this reactor core has the row of the burning at least partially ripple multiple hexagonal configuration nuclear fission module be arranged in wherein and the position be included in relative to nuclear fission module with width " x ";
Fig. 5 is the cross-sectional view of multiple adjacent hexagonal shape nuclear fission module, and except fuel rod, this nuclear fission module also has many can vertically move control rod;
Fig. 5 A is the cross-sectional view of multiple adjacent hexagonal shape nuclear fission module, except fuel rod, this nuclear fission module also have many be arranged in wherein can proliferation regeneration rod;
Fig. 5 B is the cross-sectional view of multiple adjacent hexagonal shape nuclear fission module, and except fuel rod, this nuclear fission module also has the many neutron relfector rods be arranged in wherein;
Fig. 5 C is the cross-sectional view of parallelepiped-shaped reactor core, and this reactor core has the regeneration blanket fuel assembly put around its inner circumferential cloth;
Fig. 6 is the view intercepted along the profile line 6-6 of Fig. 5;
Fig. 7 is multiple adjacent nuclear fission module and the partial vertical sectional view belonging to flow control assembly and the respective multiple flow regulation subassemblies be coupled with nuclear fission module;
Fig. 8 is the perspective exploded view of flow regulation subassembly;
Fig. 8 A is the partial vertical section exploded view of flow regulation subassembly;
Fig. 8 B is the part sectioned view opening configuration down-off adjustment subassembly allowing fluid to flow through completely;
Fig. 8 C is the part sectioned view that the closedown configuration down-off stoping fluid to flow through completely regulates subassembly;
Fig. 8 D is the view intercepted along the profile line 8D-8D of Fig. 8 B, shows the anti-rotation configuration belonging to flow regulation subassembly bottom with horizontal cross-section;
Fig. 8 E is the vertical cross section that for the sake of clarity part of flow regulation subassembly bottom has removed, shows and can rotate freely joint;
Fig. 9 is coupled with nuclear fission module and is in the partial front figure allowing fluid to flow to the flow regulation subassembly on the fully open position of nuclear fission module;
Figure 10 is coupled and is in the partial front figure that anti-fluid flows to the flow regulation subassembly in the complete off-position of nuclear fission module with nuclear fission module;
The vertical cross section of multiple flow regulation subassemblies that Figure 11 is multiple adjacent nuclear fission module and is coupled with one of nuclear fission module;
Figure 12 is the vertical cross section of multiple adjacent nuclear fission module and the respective multiple flow regulation subassemblies be coupled with nuclear fission module, this flow regulation subassembly be displayed on allow convertible fluids to flow through open completely, part closes or on the position opening and close completely;
Figure 13 is the skeleton view that for the sake of clarity part of the balladeur train subassembly belonging to flow control assembly has removed;
Figure 14 is multiple adjacent nuclear fission module and the vertical cross section being arranged in the multiple sensors in respective of nuclear fission module;
Figure 15 is the partial front figure that for the sake of clarity part of multiple flow regulation subassembly has removed, and selected one of multiple flow regulation subassembly is passed through by the rotary actuation of lead screw device with by the engagement of one of the axial multiple tubular keys driven of toothed gearing;
Figure 16 is the skeleton view of the toothed gearing of the optional person driving multiple tubular key;
Figure 17 is the partial front figure removed by for the sake of clarity part of the selected multiple flow regulation subassemblies engaged of multiple tubular key, and tubular key is at least partly by controlling with the sealed electric-motor device of controller or control module electric coupling;
Figure 18 is the partial front figure removed by for the sake of clarity part of the selected multiple flow regulation subassemblies engaged of multiple tubular key, and the sealed electric-motor device belonging to the transmitting set-acceptor device of controller or control module that tubular key can send radiofrequency signal by response at least partly controls;
Figure 19 is the partial front figure of multiple flow regulation subassemblies of the selected engagement by multiple tubular key, and tubular key controls by the fiber optic emitter-acceptor device belonging to control module that can send signal by light beam at least partly;
Figure 20 A-20S is the process flow diagram of the exemplary methods running fission-type reactor; And
Figure 21 A-21H is the process flow diagram of the exemplary methods of assembling flow control subassembly.
Embodiment
In the following detailed description, with reference to the accompanying drawing forming its part.In the drawings, the parts that similar symbol ordinary representation is similar, unless the context requires otherwise.Be described in the exemplary embodiments in detailed description, accompanying drawing and claims and do not mean that and limit the scope of the invention.Utilize other embodiment with can not departing from the spirit or scope of the theme shown herein, and other change can be made.
In addition, for the purpose of clearly showing, the application employs pro forma generality title.But, should be understood that, the object of these generality titles for showing, can discuss dissimilar theme and (such as, can describe equipment/structure and/or can discussion process/operation under structure/prelude under process/operation title in whole application; And/or the description of single topic can cross over two or more topic titles).Therefore, the use of pro forma generality title is intended to limit the scope of the invention anything but.
In addition, theme as herein described sometimes illustrates and is included in other different parts, or the different parts that parts different from other connect.Should be understood that the framework described like this is only exemplary, in fact, many other frameworks realizing identical function can be realized.From concept, " contact " realizes any arrangement of the parts of identical function, to realize desired function effectively.Therefore, combine any two parts realizing specific function herein and can regard as mutually " contact ", make independently to realize desired function with framework or intermediate member.Equally, any two parts of contact like this also can regard as mutual " being operably connected " or " being operationally coupled " of realizing desired function, and any two parts that can so contact also can regard as mutual " can operational coupled " that realize desired function.Can operational coupled special case including, but not limited to physically can match and/or the parts that physically interact, can wireless interaction and/or wireless interaction parts and/or interact in logic and or/can interact parts in logic.
In some cases, one or more parts may be called as in this article " being configured to ", " can be configured to ", " can operate/operate ", " be applicable to/be applicable to ", " can ", " can according to/according to " etc.Those of ordinary skill in the art should be realized that, " be configured to ", " can be configured to ", " can operate/operate ", " be applicable to/be applicable to ", " can ", " can according to/according to " etc. generally can comprise active state parts, inactive state parts and/or waiting status parts, unless the context otherwise requires.
About the disclosure, as previously mentioned, in many cases, for each neutron absorbed in fissilenuclide, a more than neutron is discharged, until fissionable atom core exhausts.This phenomenon is used in business nuclear reactor, with the continuous heat produced and for generating electricity.
But, due to " peak " temperature (the instant heating channel peak factor) caused by the uneven Neutron flux distribution in reactor core, the fire damage to reactor structural material may be there is.As well known in the art, neutron flux is defined by the quantity of time per unit by the neutron of unit area.This peak temperature is distributed by uneven control rod/fuel rod again and causes.If peak temperature exceedes material limits, just fire damage may be there is.In addition, the reactor operated in fast neutron spectrum may be designed to have be present in around reactor core can breed fuel " regeneration blanket " material.Such reactor will be tending towards making fuel reproduction become regeneration blanket material by neutron-absorbing.Which results in along with reactor terminates close to fuel recycle, the output power of reactor periphery increases.In the running temperature that reactor fuel circulation starts to make cooling medium flow through peripheral assembly and can keep safe, and take into account and increase along with burnup increases the power that will occur during fuel recycle.
Due to fuel " burnup ", create " reaction " (that is, change of reactor capability).The energy fluence that the fuel that burnup is defined as per unit mass usually generates, expresses with the unit in megawatt day per metric ton heavy metal (MWd/MTHM) or m. gigawatt (GW) sky per metric ton heavy metal (GWd/MTHM) usually.More particularly, " reactions change " and reactor produce more relevant than keeping the relative capacity of neutron that the exact amount of critical chain reaction is many or few.The response of reactor characterizes into the time-derivative of the reactions change increasing with making the power index of reactor or reduce usually.
About this respect, the control rod be made up of neutron absorber material is generally used for adjustment and controls reacting condition.Make such control rod pass in and out reactor core back and forth, to control neutron-absorbing changeably in reactor core, therefore control neutron-flux level and reactivity.Neutron-flux level reduces near control rod, and may be higher in away from the region of control rod.Therefore, neutron flux is uneven in whole reactor core.Which results in fuel burn-up in those regions that neutron flux is higher higher.In addition, the those of ordinary skill of nuclear energy power generation field can be understood, neutron flux and power density change are caused by many factors.May be also may not be principal element from control rod distance.Such as, neutron flux does not nearby have the reactor core border of control rod significantly declines usually.These effects may cause again the overheated or peak temperature in those regions that neutron flux is higher.Such peak temperature may because changing the engineering properties of structure but not shortening the operation life of the structure standing such peak temperature as desired.In addition, the reactor capability density proportional with the product of neutron flux and fissionable fuel concentration, by core structural material injury-free bear such peak temperature ability limit.
Therefore, with reference to Fig. 1, only as an example and without limitation, Fig. 1 shows the fission-type reactor being referred to as 10, processing the concern enumerated above.As hereafter more fully described, reactor 10 can be row ripple fission-type reactor.Fission-type reactor 10 produces the electric power being transferred to power consumer on plurality of transmission lines (not shown).Reactor 10 can alternatively for carrying out as determining that temperature is on the test the test of the impact of pile materials.
With reference to Fig. 1,1A, 1B and 2, reactor 10 comprises the fission-type reactor reactor core being referred to as 20, and fission-type reactor reactor core 20 comprises multiple fission fuel assemblies, or also as is herein referred, nuclear fission module 30.Fission-type reactor reactor core 20 leaves in reactor core housing 35 hermetically.Only as an example and without limitation, as shown in the figure, each nuclear fission module 30 can form the structure of xsect hexagonal configuration, make compared with other shape of great majority of the nuclear fission module 30 as cylindrical or spheroidal, more nuclear fission module 30 closely can be deposited in reactor core 20 together.Each nuclear fission module 30 comprises the many fuel rods 40 generated heat due to above-mentioned fission chain reaction process.If necessary, fuel rod 40 can be surrounded with fuel rod cylinder 43, to increase the structural rigidity of nuclear fission module 30 and to isolate nuclear fission module 30 one by one.Isolation nuclear fission module 30 avoids the horizontal cooling medium cross flow one between adjacent nuclear fission module 30 one by one.Horizontal cooling medium cross flow one is avoided to prevent the transverse vibration of nuclear fission module 30.Otherwise such transverse vibration may increase the risk of damage fuel rod 40.In addition, as hereafter more fully described, isolating nuclear fission module 30 one by one and making it possible to module ground controlled cooling model agent stream one by one.Control to separately, the cooling medium stream of preliminary election nuclear fission module 30 as substantially guiding cooling medium stream such according to the uneven temperature distribution in reactor core 20, effectively manage the cooling medium stream in reactor core 20.Cylindrical shell 43 can comprise puts superincumbent annular shoulder 46 (see Fig. 7) by the fuel rod bundled.When exemplary sodium cooling reactor, at normal operation period, cooling medium can have about 5.5m
3/ s (that is, about 194 cubes of ft
3/ s) average nominal volumetric flow rate and the average rated speed of about 2.3m/s (that is, about 7.55ft/s).Fuel rod 40 is adjacent one another are, defines the coolant flow channel 47 (see Fig. 7) of the flows outside making cooling medium along fuel rod 40 therebetween.Fuel rod 40 is bundled, to form aforementioned sexangle nuclear fission module 30.Although fuel rod 40 is adjacent one another are, but according to the technology that the those of ordinary skill of power producer design field is known, the pack-thread 50 (see Fig. 7) along the length spiral extension of every root fuel rod 40 still makes fuel rod 40 keep in spaced relation.
With particular reference to Figure 1B, every root fuel rod 40 has the end to end multiple fuel balls 60 be stacked on wherein.Fuel ball 60 is surrounded hermetically by fuel rod clad material 70.Fuel ball 60 comprises the above-mentioned fissilenuclide as uranium-235, uranium-233 or plutonium-239.Alternately, fuel ball 60 can comprise the bred nucleic as thorium-232 and/or uranium-238, and they change in quality into the fissilenuclide just mentioned above in fission process.Further substitute and be, fuel ball 60 can comprise fissilenuclide and can breed the predetermined mixture of nucleic.More particularly, only as an example and without limitation, fuel ball 60 can by being basically made up of oxide that selecting in the group forming as follows: uranium monoxide (UO), uranium dioxide (UO
2), thorium anhydride (ThO
2) (also referred to as thoria), orange oxide (UO
3), urania-plutonium oxide (UO-PuO), triuranium octoxide (U
3o
8) and composition thereof.Alternately, fuel ball 60 can mainly comprise and other metal alloy as (but being not limited to) zirconium or thorium metal or unalloyed uranium.Substitute as another, fuel ball 60 mainly can comprise the carbonide (UC of uranium
x) or the carbonide (ThC of thorium
x).Such as, fuel ball 60 can by being basically made up of carbonide that selecting in the group forming as follows: uranium monocarbide (UC), uranium dicarbide (UC
2), uranium sesquicarbide (U
2c
3), thorium dicarbide (ThC
2), thorium carbide (ThC) and composition thereof.As another non-limitative example, fuel ball 60 can by being basically made up of nitride that selecting in the group forming as follows: uranium nitride (U
3n
2), uranium nitride-zirconium nitride (U
3n
2zr
3n
4), plutonium uranium nitride ((U-Pu) N), thorium nitride (ThN), U-Zr alloy (UZr) and composition thereof.The fuel rod clad material 70 surrounding fuel ball 60 in heaps hermetically can be the picture ZIRCOLOY of known anticorrosive and resistance to fracture
tMthe suitable zircaloy that (registered trademark of Westinghouse Electrical Corp. (Westinghouse ElectricCorporation)) is such.Cladding materials 70 also can be made up of other material as ferrito-martensite steel.
Can the best see from Fig. 1, reactor core 20 is disposed in reactor pressure vessel 80, leaks into surrounding biologic circle to prevent radioactive particle, gas or liquid from reactor core 20.Pressure vessel 80 can be the steel of suitable size and thickness, concrete or other materials, to reduce the risk of such radiation leakage and to support required pressure load.In addition, the containment (not shown) of the part surrounding reactor 10 hermetically may be there is, to strengthen preventing radioactive particle, gas or liquid from leaking into the guarantee of surrounding biologic circle from reactor core 20.
Referring again to Fig. 1, major loop cooling tube 90 is coupled with reactor core 20, makes suitable cooling medium can flow through reactor core 20, so that cooled reactor reactor core 20.Major loop cooling tube 90 can be made up of any suitable material as stainless steel.Can understand, if necessary, major loop cooling tube 90 not only can be made up of ferroalloy, and can be made up of nonferrous alloy, zirconium-base alloy or other structured material or compound.The cooling medium that major loop cooling tube 90 transmits can be the potpourri of inert gas or inert gas.Alternately, cooling medium can be picture " gently " water (H
2or gaseous state or supercritical carbon dioxide (CO O)
2) such other fluid.As another example, cooling medium can be liquid metal.Such liquid metal can be lead (Pi) alloy as lead-bismuth (Pb-Bi).Further, cooling medium can be the organic coolant as polyphenyl or fluorocarbon.In one exemplary embodiment disclosed herein, cooling medium can be suitably Liquid Sodium (Na) metal or the sodium metal mixture as sodium-potassium (Na-K).As an example, depend on specific reactor core design and running history, the normal operating temperature of sodium cooling reactor core may be relatively high.Such as, when having 500 to 1,500 megawatt sodium cooling reactor of mixing uranium-plutonium oxide fuel, can from about 510 DEG C (namely in normal operation period reactor core outlet temperature, 950 °F) to about 550 DEG C (that is, 1,020 °F).On the other hand, in LOCA (coolant loss accident) or LOFTA (the of short duration forfeiture accident of flow) period, depend on reactor core design and running history, (namely fuel can peak temperature may reach about 600 DEG C, 1,110 °F) or higher.In addition, the decay heat accumulation after LOCA and after LOFTA during situation and during reactor operation suspension may cause unacceptable heat built-up.Therefore, in some cases, the cooling medium stream controlling to reactor core 20 during situation after normal operation situation and accident is suitable.
In addition, the temperature curve in reactor core 20 as position function and become.About this respect, the Temperature Distribution in reactor core 20 may immediately following the power density space distribution in reactor core 20.As everyone knows, when lacking around the suitable neutron relfector around reactor core 20 or neutron reproduction " blanket ", the power density of reactor core 20 immediate vicinity is generally higher than the power density of reactor core 20 near its circumference.Therefore, expect, the cooling medium stream parameter of the nuclear fission module 30 of reactor core 20 near its circumference will be less than the cooling medium stream parameter of the nuclear fission module 30 of reactor core 20 immediate vicinity, especially when the reactor core life-span just starts.Therefore, in this case, will there is no need to provide identical or Homogeneous cooling agent mass velocity to each nuclear fission module 30.As detailed below, provide following technology: depend on the position of nuclear fission module 30 in reactor core 20 and desired reactor operation result, change to the cooling medium stream of each nuclear fission module 30.
Still, with reference to Fig. 1, described in current, the band hot coolant that reactor core 20 generates flows to intermediate heat exchanger 100 along coolant flow paths 95.The cooling medium flowed along coolant flow paths 95 flows through intermediate heat exchanger 100, flows in the pumping chamber 105 be associated with intermediate heat exchanger 100.After in inflow pumping chamber (plenum volume) 105, as shown in multiple arrow 107, cooling medium continues to flow through major loop pipeline 90.Can understand, owing to occurring in the heat transfer in intermediate heat exchanger 100, the cooling medium leaving pumping chamber 105 cools.First pump 110 is coupled with major loop pipeline 90, and the reactor coolant fluid transmitted with major loop pipeline 90 is communicated with, so that by major loop pipeline 90, by reactor core 20, along coolant flow paths 95, reactor coolant is pumped into intermediate heat exchanger 100, and enters in pumping chamber 105.
Referring again to Fig. 1, be equipped with the subloop pipeline 120 removing heat from intermediate heat exchanger 100.Subloop pipeline 120 comprises pair " heat " branch road pipeline section 130 and secondary " cold " branch road pipeline section 140.As shown in the figure, secondary cold branch road pipeline section 140 forms entirety with the hot branch road pipeline section 130 of pair, to form the closed-loop path defining subloop pipeline 120.It can be suitably the fluid of Liquid Sodium or Liquid Sodium potpourri that the subloop pipeline 120 defined by pair hot branch road pipeline section 130 and the cold branch road pipeline section 140 of pair comprises.Owing to just describing, secondary hot branch road pipeline section 130 extended to steam generator and superheater assembly 143 (hereinafter referred to as " steam generator 143 ") from intermediate heat exchanger 100.By after steam generator 143, owing to occurring in the heat transfer in steam generator 143, flow through subloop pipeline 120 and be in than entering in steam generator 143 temperature low before with the cooling medium leaving steam generator 143.By after steam generator 143, along " cold " branch road pipeline section 140 terminated on intermediate heat exchanger 100, as pumping cooling medium by the second pump 145.Hereafter the mode that steam generator 143 generates water vapour will usually be described immediately.
Also referring again to Fig. 1, being in steam generator 143 is the water body 150 remained on predetermined temperature and pressure.Its heat is given the water body 150 be in the temperature lower than the fluid flowing through secondary hot branch road pipeline section 130 by the fluid flowing through secondary hot branch road pipeline section 130.Along with its heat is given water body 150 by the fluid flowing through secondary hot branch road pipeline section 130, a part of water body 150 flashes to water vapour 160 by according to the temperature in steam generator 143 and pressure.Then, water vapour 160 will be advanced by steam pipe 170, one end of steam pipe 170 and water vapour 160 vapor communication, and the other end and water body 150 fluid connection.Rotary turbine 180 is coupled with steam pipe 170, so that turbine 180 passes therethrough along with water vapour 160 and rotates.Generate electricity as the generator 190 be connected with turbine 180 by revolving wormgear arbor 195 rotates along with turbine 180.In addition, condenser 200 is coupled with steam pipe 170, receives the water vapour by turbine 180.Condenser 200 makes water recovery become aqueous water, and passes to as cooling tower 210 by any used heat, the heating radiator be associated with reactor 10.By being inserted in the 3rd pump 220 between condenser 200 and steam generator 143, the aqueous water condensed by condenser 200 is pumped into steam generator 143 along steam pipe 170 from condenser 200.
Forward Fig. 2 to now, 3 and 4, they show the exemplary configuration of nuclear reactor 20 with cross-sectional form.About this respect, nuclear fission module 30 can be arranged as reactor core 20 and define the hexagonal configuration configuration being referred to as 230.Alternately, nuclear fission module 30 can be arranged as reactor core 20 and define the cylindrical shape configuration being referred to as 240.Substitute as another kind, nuclear fission module 30 can be arranged as reactor core 20 and define the parallelepiped-shaped configuration being referred to as 250.About this respect, due to reason provided below, reactor core 250 has first end 252 and the second end 254.
With reference to Fig. 5, have nothing to do with the configuration selected for reactor core 20, many separated, extending longitudinally and can vertically move control rod 260 be arranged in symmetrically along predetermined quantity nuclear fission module 30 length to extend control rod guide tube or involucrum (not shown) in.Be shown as the neutron fission reaction that the control rod 260 be arranged in predetermined quantity hexagonal configuration nuclear fission module 30 controls to occur in nuclear fission module 30.Control rod 260 comprises the suitable neutron absorber material having and can accept large neutron-absorption cross-section.About this respect, absorbing material can be basically by the metal selected in the group formed as follows or metalloid: lithium, silver, indium, cadmium, boron, cobalt, hafnium, dysprosium, gadolinium, samarium, erbium, europium and composition thereof.Alternately, absorbing material can be basically by the compound selected in the group formed as follows or alloy: silver-colored indium cadmium alloy, boron carbide, zirconium diboride, titanium diboride, hafnium boride, metatitanic acid gadolinium, metatitanic acid dysprosium and composition thereof.Control rod 260 controllably provides negative reaction to reactor core 20.Therefore, control panel 260 provides reaction manager ability to reactor core 20.In other words, control rod 260 can control or be configured to the neutron flux curve controlling to stride across reactor core 20, and therefore impact strides across the temperature curve of reactor core 20.
With reference to Fig. 5 A and 5B, there is illustrated the alternate embodiments of nuclear fission module 30.Can understand, nuclear fission module 30 is without the need to neutron activation.In other words, nuclear fission module 30 is without the need to comprising any fissile material.In this case, nuclear fission module 30 can be pure reflection subassembly or pure can breeder assembly, or both assemblys.About this respect, nuclear fission module 30 can be comprise the reproducing kernel fission module of core regrown material or comprise the reflective core fission module of reflecting material.Alternately, in one embodiment, nuclear fission module 30 can regenerate rod with core or reflect excellent combination and comprise fuel rod 40.Such as, in fig. 5, many can be combined with fuel rod 40 and to be arranged in nuclear fission module 30 by fertile nuclei regeneration rod 270.Also control rod 260 can be there is.As described above, in core regeneration rod 270 can fertile nuclei regrown material can be thorium-232 and uranium-238.Like this, nuclear fission module 30 defines can fertile nuclei regeneration module.In figure 5b, many neutron relfectors rod 274 is combined with fuel rod 40 is arranged in nuclear fission module 30.Also control rod 260 can be there is.Reflecting material can be basically by the material selected in the group formed as follows: beryllium (Be), tungsten (W), vanadium (V), depleted nuclear fuel (U), thorium (Th), lead alloy and composition thereof.In addition, reflection rod 274 also can be selected from diversified steel alloy.Like this, nuclear fission module 30 defines neutron relfector assembly.The those of ordinary skill of core in-core fuel management aspect can be understood, nuclear fission module 30 can comprise any appropriately combined of nuclear fuel rod 40, control rod 260, regeneration rod 270 and reflection rod 274.
Fig. 5 C shows another embodiment of previous reaction heap reactor core 250.In figure 5 c, around surrounding's disposed inboard of parallelepiped-shaped reactor core 250 and comprise that have can the regeneration blanket of multiple reproducing kernels fission modules 276 of fertile material.Regeneration blanket regenerates fissile material wherein.
Turn back to Fig. 4, have nothing to do with the configuration selected for nuclear fission module 20, fission-type reactor reactor core 20 can be configured to the row ripple fission-type reactor reactor core as exemplary reactor core 250.About this respect, can the relatively little and dismountable nuclear fission igniter 280 of moderate enriched isotope of fissionable material suitably be placed in reactor core 250 without limitation as U-233, U-235 or Pu-239 will be comprised.Only as an example and without limitation, lighter 280 can be placed near the first end 252 relative with the second end 254 of reactor core 250.Lighter 280 discharges neutron.The neutron that lighter 280 discharges is by fissible in nuclear fission module 30 and/or can catch by fertile material, causes chain reaction of nuclear fission.If necessary, once chain reaction becomes self-holding, just lighter 280 can be removed.
Referring again to Fig. 4, lighter 280 causes three-dimensional, detonation row ripple or " combustion wave " 290 with width " x ".When the neutron that lighter 280 discharges it causes " igniting ", combustion wave 290 is outwards advanced from the lighter 280 near first end 252, goes to the second end 254 of reactor core 250, to form propagating burning ripple 290.In other words, each nuclear fission module 30 can both pass reactor core 250 along with combustion wave 290 and receive the row ripple 290 that burns at least partially.The speed of burning row ripple 290 can be constant or non-constant.Therefore, can control combustion ripple 290 propagate speed.Such as, vertically move with predetermined or programming mode the neutron reaction that aforementioned control rod 260 (see Fig. 5) can drive or reduce the fuel rod 40 be arranged in nuclear fission module 30 downwards.Like this, the neutron reaction driving or reduce the current fuel rod 40 burnt on the position of combustion wave 290 is downwards compared relative to the neutron reaction of " unburned " fuel rod 40 before combustion wave 290.This result gives the combustion wave direction of propagation of arrow 295 indication.
Co-pending U.S. patent application the 11/605th while on November 28th, 2006 is " Automated Nuclear Power Reactor For Long-Term Operation (the automatic power producer of long-time running) " with the submission of the name of the people such as RoderickA.Hyde and denomination of invention, the ultimate principle of such row ripple fission-type reactor is disclose in more detail in No. 943, this application has transferred the assignee of the application, is incorporated herein by its whole open text by reference at this.
With reference to Fig. 6 and 7, there is illustrated upright adjacent hexagonal shape nuclear fission module 30.Although merely illustrate three adjacent nuclear fission modules 30, should be understood that to there is a large amount of nuclear fission module 30 in reactor core 20.In addition, each nuclear fission module 30 comprises many foregoing fuel rods 40.Each nuclear fission module 30 is installed on horizontal-extending reactor core lower supporting plate 360.Reactor core lower supporting plate 360 strides across all nuclear fission modules 30 and extends.Due to reason provided below, reactor core lower supporting plate 360 has the relative opening (counter pore) 370 passed therethrough.Relative opening 370 has the openend 380 allowing cooling medium to flow into.Stride across the top of each nuclear fission module 30 or exit portion horizontal-extending and what be removably attached thereto is the reactor core upper backup pad 400 covering each nuclear fission module 30.Reactor core upper backup pad 400 also defines the multiple chutes 410 allowing cooling medium to flow therethrough.
As previously mentioned, the configuration selected with reactor core 20 has nothing to do, and importantly controls the temperature of reactor core 20 and nuclear fission module 30 wherein.Due to several respects reason, suitable temperature controls very important.Such as, if peak temperature exceedes material limits, then may cause fire damage to reactor core structure material.Such peak temperature may because changing the engineering properties of structure, those especially relevant with thermal creep character but not shorten the operation life of the structure standing such peak temperature as desired.In addition, the ability that reactor capability density bears such high temperature by core structural material injury-freely limits.In addition, reactor 10 can alternatively for carrying out as determining that temperature is on the test the test of the impact of pile materials.Controlling reactor core temperature is important for successfully carrying out such test.In addition, when lacking around the neutron relfector around reactor core 20 or neutron reproduction blanket, to reside in reactor core 20 in the heart or neighbouring nuclear fission module 30 can generate heat than residing in nuclear fission module more than 30 upper or neighbouring around reactor core 20.Therefore, because reactor core 20 immediate vicinity will involve the coolant mass flow rate higher than the nuclear fission module 30 of the near its circumference of reactor core 20 compared with thermonuclear fission module 30, provide Homogeneous cooling agent mass velocity to be inadequate so stride across reactor core 20.Disclosing herein provides these technology paid close attention to of process.
With reference to figure 1,6 and 7, reactor coolant is flowed to nuclear fission module 30 along the coolant flow paths of flow arrow 420 indication or fluid stream by the first pump 110 and major loop 90.Then, reactor coolant continues to flow along coolant flow paths 420, flows through the openend 380 formed in lower supporting plate 360.As described in more detail below, take away selected by nuclear fission module 30 that heat or cooling be on the position of burning row ripple 290 several in several selected by the nuclear fission module 30 that reactor coolant may be used for from the position being in burning row ripple 290.As described in more detail below, nuclear fission module 30 can whether to be in nuclear fission module 30 according to combustion wave 290 at least partly or near, whether in nuclear fission module 30 or near detect or otherwise whether to reside in nuclear fission module 30 or neighbouringly to select.
Referring again to Fig. 1,6 and 7, in order to reach result desired by selected that cools nuclear fission module 30, regulated by adjustable flow subassembly 430 to be coupled with nuclear fission module 30.Flow regulation subassembly 430 responds combustion wave 290 (see Fig. 4) relative to the position of nuclear fission module 30 and the flow responding some the operational factor controlled cooling model agent relevant with nuclear fission module 30.In other words, flow regulation subassembly 430 can or be configured to, when there is combustion wave 290 (that is, the combustion wave 290 that intensity is less) comparatively in a small amount in nuclear fission module 30, the cooling medium of relative small number is supplied to nuclear fission module 30.On the other hand, flow regulation subassembly 430 can or be configured to, when there is relatively large combustion wave 290 (that is, the combustion wave 290 that intensity is larger) in nuclear fission module 30, the cooling medium of relative a greater number is supplied to nuclear fission module 30.The existence of combustion wave 290 and intensity can be identified by the rate of heat production, neutron-flux level, power level or other suitable operation characteristic relevant with nuclear fission module 30.
With reference to Fig. 7,8,8A, 8B, 8C, and 8D, adjustable flow regulates subassembly 430 to be extended by relative opening, to regulate the flow entering the fluid stream of nuclear fission module 30.Those of ordinary skill in the art can understand, in order to regulate the flow of fluid stream 420, flow regulation subassembly 430 is equipped with controlled flow resistance.It is several separately that flow regulation subassembly 430 comprises that the substantial cylindrical first with many first pore zones 460 or outer tube 450, first pore zone 460 define around radially-arranged multiple axially-spaced first hole of outer tube 450 or the first controllable flow gap 470.Due to reason provided below, outer tube 450 comprises first joint 480 can with hexagonal configuration xsect further.Due to reason provided below, the first joint 480 defines threaded inner portion cavity 500.
Referring again to Fig. 7,8,8A, 8B, 8C, and 8D, as hereafter open more in detail, flow regulation subassembly 430 comprises further can be received into substantial cylindrical second in outer tube 450 or inner sleeve 530 spirally.In one embodiment, inner sleeve 530 and nuclear fission module 30 can be made to form entirety, so that inner sleeve 530 is permanent sections of nuclear fission module 30 during manufacture nuclear fission module 30.In another embodiment, inner sleeve 530 can removably be connected with nuclear fission module 30, so that inner sleeve 530 can easily separate with nuclear fission module 30, is not therefore the permanent sections of nuclear fission module 30.In any embodiment, what inner sleeve 530 all comprised that many second pore zone 540, second pore zones 540 define around radially-arranged multiple axially-spaced second hole of inner sleeve 530 or the second controllable flow gap 550 is several separately.Inner sleeve 530 comprises size further and makes external belt screw thread second joint 560 in the threaded inner portion cavity 500 that can be received into the bottom 490 belonging to outer tube 450 spirally.The top 570 of inner sleeve 530 comprises a cap 580, and as previously mentioned, cylinder cap 580 for good and all also for good and all can not form entirety with nuclear fission module 30.Endoporus 590 is extended by top 570, comprises by cylinder cap 580, to allow cooling medium pass therethrough.What be coupled with cylinder cap 580 and fuel rod 580 can be the conical butt funnel part 600 with inside surface 605, conical butt funnel part 600 is communicated with the inside of endoporus 590 with cylindrical shell 43, to make cooling medium pass through from endoporus 590 to cylindrical shell 43 ground that fuel rod 40 is resident.As previously mentioned, nuclear fission module 30 can cause or be configured to cause temperature correlation reactions change.Therefore, the flow control adjustment subassembly 430 cooling medium stream be configured at least partly by controlling to nuclear fission module 30 controls the temperature in nuclear fission module 30, to affect such temperature correlation reactions change.
Referring now to Fig. 8 A and 8D, the bottom 490 of outer tube 450 comprises the anti-rotation configuration being referred to as 606, rotates relative to inner sleeve 530 to prevent outer tube 450.About this respect, outer tube 450 defines the multiple grooves as groove 607a and 607b, matingly to receive respective one of multiple teat 608a and 608b forming entirety with inner sleeve 530.Therefore, along with outer tube 450 rotates, due to teat 608a and 608b respectively with the engaging of groove 607a and 607b, prevent inner sleeve 530 to rotate relative to outer tube 450.
Can the best see from Fig. 8 E, the first joint 480 can rotate relative to outer tube 450.About this respect, the first joint 480 comprises the annular flange 608c in the ring groove 608d being slidably received within and being formed in outer tube 450.Like this, the first joint 480 can slidably rotate relative to outer tube 450.First joint 480 can slidably rotate along any one direction of curved arrow 608e or 608f indication.In addition, along with the first joint 480 is as the direction along arrow 608e, automatically rotate slidably along an aspect, threaded inner portion cavity 500 can engage with the external thread of the second joint 560 spirally.Can understand, along with the screw thread of internal cavities 500 can engage with the external thread of the second joint 560 spirally, first joint 480 as on surperficial 608g near the first sleeve pipe 450, along with the first joint 480 near the first sleeve pipe 450, first sleeve pipe 450 by the direction of vertical arrows 408h indication along along upwards translation or the rising of its longitudinal axis.Owing to there is only upwards translation or the rising in the direction of arrow 608h of anti-rotation configuration the 608, first sleeve pipe 450.Along with the first sleeve pipe 450 upwards translation or rising scheduled volume, the first hole 470 will be closed by the second pore zone 540 of inner sleeve 530 gradually, covers, blocks, and otherwise blocking.In addition, can understand, along with the first sleeve pipe 450 upwards translation or rising scheduled volume, the second hole 550 will be closed by the first pore zone 460 of outer tube 450 gradually, covers, blocks, and otherwise blocking.Close gradually by this way, cover, block, and otherwise blocking the first hole 470 and the second hole 550 reduce the flow of cooling medium by the first hole 470 and the second hole 550 changeably.Can understand, first interface 480 is as the direction along curved arrow 608f, rotation in the opposite direction makes the first hole 470 and the second hole 550 open gradually, opens, discloses and otherwise dredge, to increase the flow that cooling medium passes through the first hole 470 and the second hole 550 changeably.
Therefore, with reference to Fig. 7,8,8A, 8B, 8C, 8D, 8E, 9 and 10, as is now described, by using two kinds of different parts one outer tubes 450 and inner sleeve 530, achieve the flow control in nuclear fission module 30 at least partly.As previously mentioned, when first time manufactures nuclear fission module 30, inner sleeve 530 and nuclear fission module 30 can be made to form entirety.But if necessary, inner sleeve can separate with nuclear fission module 30 and formed, but is attached thereto, instead of when first time manufactures nuclear fission module 30, form entirety with nuclear fission module 30.Inner sleeve 530 defines and allows cooling medium by entering multiple second holes 550 of nuclear fission module 30.Outer tube 450, at the sliding outside of inner sleeve 530, has corresponding multiple first hole 470.Outer tube 450 and inner sleeve 530 be concentric, and hole 470/550 is always aimed at, so that radially or turning axle coupling.The flow of cooling medium is controlled at the relative position of axis or vertical direction by inner sleeve 530 and outer tube 450.About this respect, Fig. 8 B shows and allows fluid to flow into completely to open the lower flow regulation subassembly 430 of configuration completely in nuclear fission module 30, and Fig. 8 C shows and stops fluid to flow into completely to close the flow regulation subassembly 430 under configuring completely in nuclear fission module 30.As previously mentioned, teat 608a and 608b and groove 607a and 607b respective one engage and limit the rotation of outer tube 450 relative to inner sleeve 530.This feature makes outer tube 450 slide axially on inner sleeve 530, but relatively between outer tube 450 with inner sleeve 530 does not rotate.The fine tuning of cooling medium stream is realized relative to sliding axially gradually of inner sleeve 530 by outer tube 450.Therefore, first joint 480 opens flow regulation subassembly 430 gradually along the rotation of direction 608e, and the first joint 480 cuts out flow regulation subassembly 430 gradually along the rotation of direction 608f, thus realize the fine tuning in hole 470/550, therefore realize the fine tuning of cooling medium stream.
The best can see can existing as flow regulation subassembly 609a and 609b from Figure 11, the multiple comparatively low discharges being assigned to single core fission module 30 regulate subassembly.Regulate subassembly 609a and 609b to be assigned to single core fission module 30 compared with low discharge to provide alternative configuration cooling medium stream being supplied to nuclear fission module 30 by multiple.In addition, by multiple regulate subassembly 609a and 609b to be assigned to separately compared with low discharge or single core fission module 30 provide fully control separately or single core fission module 30 different piece in the possibility of Temperature Distribution.Having this may be because can control respectively by each fluid flow regulating subassembly 609a and 609b compared with low discharge.
With reference to Figure 12,13,14,15, and 16, there is illustrated adjustment or regulate the flow regulation subassembly 430 entered under the running status of the cooling fluid flow of nuclear fission module 30.As hereafter more fully open, flow regulation subassembly 430 defines the flow control assembly being referred to as 615 together with balladeur train subassembly 610.In other words, flow control assembly 615 comprises flow regulation subassembly 430 and balladeur train subassembly 610.About this respect, balladeur train subassembly 610 is disposed in as below reactor core lower supporting plate 360 below reactor core 20, can or be configured to be coupled with flow regulation subassembly 430, to adjust flow regulation subassembly 430.As previously mentioned, adjust flow regulation subassembly 430 and can control the cooling medium stream entering nuclear fission module 30 changeably.In addition, if necessary, outer tube 450 can be sent to nuclear fission module 30 by balladeur train subassembly 610.
With reference to Figure 13,14,15, and 16, the configuration of balladeur train subassembly 610 is described now.Balladeur train subassembly 610 comprises crosses over the long bridge 620 of reactor core 20, so as by multiple can above vertically moving sleeve spanner 630 be supported on.Due to hereafter disclosed reason, each tubular key 630 has rotating shaft 700, and is movably disposed within sleeve well 635, and what be connected with the opposite end of bridge 620 is first move bridge device 640a and second and move bridge device 640b respectively.Move the toothed gearing (also not shown) that bridge device 640a and 640b drive by motor (not shown) to operate.Such motor can be positioned at the outside of reactor core 20, cycles through the corrosive attack that reactor core 20 causes and heat to avoid the cooling medium as Liquid Sodium.Each bridge device 640a and 640b that move at least comprises wheel 650a and 650b respectively, to make to move bridge device 640a and 640b simultaneously along the respective movement being spaced laterally apart parallel orbit 660a and 660b.Move bridge device 640a and 640b can or to be configured in any one direction of arrow 663 indication along track 660a and 660b travelling bridge 620.That be connected with each track 660a and 660b can be rail supporting body 665a and 665b respectively, so that above being supported on by track 660a and 660b.
With reference to Figure 13,14,15,16,17, and 18, tubular key 630 is configured to be in vertical reciprocating motion in sleeve well 635, engages with the first joint 480 of outer tube 450 and departs from.In an embodiment of balladeur train subassembly 610, the lead screw device that several row tubular key 630 is configured to by being referred to as 670 is driven.Lead screw device 670 has the lead screw 680 being configured to the external thread 690 that can engage spirally around the rotating shaft 700 belonging to each tubular key 630.Lead screw 680 can be driven by the mechanical drive system 705 comprising the mechanical linkage 707 be coupled with lead screw 680.When mechanical linkage 707 drives lead screw 680, due to lead screw 680 and the screw-threaded engagement around the external thread 690 of rotating shaft 700, lead screw 680 will rotate or rotating shaft 700.As shown in the figure, when the hexagonal configuration recess 700a on rotating shaft 700 top engages with hexagonal configuration first joint 480, to rotate or rotating shaft 700 will make the one the first joints 480 rotate or rotate equal number.
With reference to Figure 15 and 16, present description is risen selectively and is reduced the mode of every root rotating shaft 700.About this respect, band external thread long mechanical linkage extension 708 engages with the first gear 709, so that along any one direction revolving first gear 709 of curved arrow 709a and 709b.Such as, along with mechanical linkage extension 708 is along one of the direction translation of double-headed arrow 709c indication, the first gear 709, by as the direction along arrow 709a, rotates along first direction.On the other hand, along with mechanical linkage extension 708 is along the reverse direction translation of double-headed arrow 709c indication, the first gear 709, by as the direction along arrow 709b, rotates along second direction.Along with the first gear 709 rotates as the direction along arrow 709a, band external thread bosom first bar 709d also rotates equal number, because the external thread of the first bar 709d can engage with the internal thread (not shown) by being formed centrally in the first gear 709 spirally.Second gear 709e has the internal thread (not shown) by being wherein formed centrally, can engage with the external thread of the first bar 709d spirally.Therefore, along with the first gear 709 rotates the first bar 709d, due to the first bar 709d and the second gear 709e screw-threaded engagement, so the second gear 709e will along the first bar 709d translation.Second gear 709e moves to the position of a predetermined rotating shaft 700 along the first bar 709d always.Can understand, the external thread of the second gear 709e or the spacing of the gear teeth are formed like this, and that is exactly do not produce interference, so that the second gear 709e can carry out without hindrance along the translation of the first bar 709e to the externally threaded spacing around rotating shaft 700.Described in current, further provided with the 3rd gear 709f.About this respect, the 3rd gear 709f is coupled with the either side and the length second bar 709g adjacent with bosom first bar 709d and long 3rd bar 709h being arranged in bosom first bar 709d.3rd gear 709f is driven by aforementioned mechanical connecting rod extension 708, and it can move to from the primary importance that the first gear 709 is coupled the second place engaged with the 3rd gear 709f.Along with the 3rd gear 709f rotates, the longitudinal axis around the first bar 709d rotates by the second bar 709g and the 3rd bar 709h, to make the second gear 709e rotate around the longitudinal axis of the first bar 709d.Along with the second gear 709e rotates, the external thread of the second gear 709e can engage with the external thread of rotating shaft 700 spirally, so that vertical translation rotating shaft 700.Like this, tubular key translation is up or down made.Can understand, mechanical linkage extension 708 can replace with the 4th gear (not shown) or pulley belt component (also not shown).
With reference to Figure 17,18 and 19, in another embodiment of balladeur train subassembly 610, tubular key 630 seals by the multiple stage be coupled with rotating shaft 700, respective one of reversible first motor 710 rotate respectively and axial translation.First motor 710 is sealings, can air cooling, to protect the first motor 710 from the corrosive attack of cooling medium and the heat effects that can be Liquid Sodium or Liquid Sodium potpourri.First motor 710 is configured to vertical mobile shaft 700 selectively.Motor 710 can along first direction or the second direction contrary with first direction running from the rotor of motor 710, the meaning moving up or down rotating shaft 700 to be respectively reversible.The running of mechanical drive system 705 or motor 710 can suitably be controlled by the controller that is coupled with it or control module 720.Every platform motor 710 can be that picture can buy such customization DC servo motor from the ARC system house (ARC Systems, Incorporated, Hauppauge, New York, USA) being located at USA New York Hauppauge.Controller 720 can be that picture can buy such customization electric machine controller from the tripod electric corporation (Bodine Electric Company, Chicago, Illinois, USA) being located at Chicago, Illinois, USA city.According to another embodiment, tubular key 630 moves respectively by transmitting set-acceptor device, this transmitting set-acceptor device comprise by receive transmitting set 740 launch radiofrequency signal operate respectively multiple stage sealing, air cooling, reversible second motor 730.Second motor 730 is sealings, can air cooling, to protect the second motor 730 from the corrosive attack of sodium cooling agent and heat effects.The power supply of the second motor 730 can be battery or other power-supply unit (not shown).The second motor 730 and the transmitting set 740 that are configured to receive such radio signal can be can from Myostat Electric Machine Control company (the Myostat Motion Control being located at Ontario, Canada, Incorporated, Ontario, Canada) the customization motor that buys and transmitter.According to another embodiment, tubular key 630 moves respectively by the fiber optic emitter-acceptor device being referred to as 742, and this fiber optic emitter-acceptor device 742 has multifiber cable 745, so that by Transmission light running reversible electric machine device.
Can the best see from Figure 14, flow control assembly 615, therefore flow regulation subassembly 433 can according to or response the operational factor relevant with nuclear fission module 30 run.About this respect, can at least one sensor 750 be arranged in nuclear fission module 30, to sense the state of operational factor.The operational factor that sensor 750 senses can be the Current Temperatures in nuclear fission module 30.Alternately, the operational factor that sensor 750 senses can be the former temperature in nuclear fission module 30.In order to sensing temperature, sensor 750 can be can from the Thermocoax company (Thermocoax being located at State of Georgia, US Alpha Li Ta, Incorporated, Alpharetta, Georgia U.S.A.) the thermopair equipment that buys or temperature sensor.Substitute as another kind, the operational factor that sensor 750 senses can be the neutron flux in nuclear fission module 30.In order to sense neutron flux, sensor 750 can be that picture can buy such " PN9EB20/25 " neutron flux proportional counter from Surrey Centronic mansion (Centronic House, Surrey, England).As another example, the operational factor that sensor 750 senses can be the characteristic isotope in nuclear fission module 30.Characteristic isotope can be fission product, activating isotope, the transformation isotope passing through regeneration formation or further feature isotope.Another example is the operational factor that sensor 750 senses can be neutron fluence in nuclear fission module 30.As technically well-known, neutron fluence is defined by the neutron flux of integration over some period of time, represents the unit area neutron number passed through at that time durations.As another example, the operational factor that sensor 750 senses can be fission module pressure, at normal operation period, for exemplary sodium cooling reactor about 10 bar (namely this fission module pressure can be, about 145psi (pound per square inch)), or for the dynamic fluid pressure of exemplary pressurization " gently " water cooling reactor about 138 bar (that is, about 2000psi).Alternately, the fission module pressure that sensor 750 senses can be static fluid pressure or fission product pressure.In order to sense dynamically or fission module pressure, sensor 750 can be can from Kaman's measuring system company (the Kaman Measuring Systems being located at Colorado Springs, Colorado, Incorporated, Colorado Springs, Colorado USA) the customization pressure detector that buys.Substitute as another kind, sensor 750 can be as " BLANCETT 1100 turbo flow meter ", can from the instrument company (Instrumart being located at Vermont ,Usa Williston, Incorporated, Williston, Vermont U.S.A.) the proper flow gauge that buys.In addition, the operational factor that sensor 750 senses can by suitably determining based on computerized algorithm.Diversified algorithm can be realized, comprise picture perfect gas law PV=nRT, or from the direct or indirect measurement of other character as flow, temperature, electrical property etc., produce those algorithms indicating the algorithm known of the signal of pressure or temperature such.According to another example, operational factor can be the action that operating personnel start to take.That is, flow regulation subassembly 430 can any suitable operational factor determined of operation response personnel adjust.Further, flow regulation subassembly 430 can be responded the operational factor determined by suitable FEEDBACK CONTROL and adjusts.In addition, flow regulation subassembly 430 can respond the operational factor that automatic control system determines and adjusts.In addition, the change that flow regulation subassembly 430 can respond decay heat adjusts.About this respect, decay heat reduces at " afterbody " of combustion wave 290 (see Fig. 4).The existence detecting the afterbody of combustion wave 290 may be used for reducing coolant flow speed in time, to take the reduction of this decay heat found at the afterbody of combustion wave 290 into account.When nuclear fission module 30 resides in after combustion wave 290, situation is especially true.In this case, flow regulation subassembly 430 decay heat of taking nuclear fission module 30 into account changes relative to the distance change of combustion wave 290 along with nuclear fission module 30.The state sensing such operational factor can contribute to the operation of suitable controlling and adjustment flow control assembly 615, the temperature therefore in suitable controlling and adjustment reactor core 20.
With reference to Figure 14,15,17,18 and 19, from following description, should be understood that flow regulation subassembly 430 can reconfigure according to the predetermined input of controller 720 and 740, so that controller 720 and 740 is combined with flow regulation subassembly 430 suitably control fluid flow.That is, the predetermined input of controller 720 and 740 is signals that sensor as aforementioned 750 produces.Such as, the predetermined input of controller 720 and 740 can be the signal that aforementioned hot galvanic couple or temperature sensor produce.Alternately, the predetermined input of controller 720 and 740 can be the signal that aforesaid fluid flowmeter produces.Substitute as another kind, the predetermined input of controller 720 and 740 can be the signal that aforementioned neutron-flux detector produces.As another example, the signal that controller 720 and 740 receives may through the process of reactor control system (not shown).Such as, the signal that such reactor control system produces can from gauge or detector, and the computing machine in reactor pulpit or operating personnel's process, then output to balladeur train subassembly 610, so that movable bridge 620 and tubular key 640 operate flow regulation subassembly 430.
With reference to Fig. 4,10 and 14, those of ordinary skill in the art should be understood that according to instruction herein, and flow control assembly 615 can arrive and/or leave the time controling of nuclear fission module 30 according to burning row ripple 290 and regulate the flow of cooling medium.In addition, flow control assembly 615 can according to burning row ripple 290 close to nuclear fission module 30 or the time controling near nuclear fission module 30 and the flow regulating cooling medium.Flow control assembly 615 can also control according to the foregoing width of combustion wave 290 " x " and regulate the flow of cooling medium.Along with combustion wave 290 is advanced by nuclear fission module 30, the arrival of combustion wave 290 and any one leaving by sensing aforementioned operational factor detect.Such as, flow control assembly 615 can control according to the rate of heat production of sensing in nuclear fission module 30 and regulate the flow of cooling medium.It should be obvious that for the person of ordinary skill of the art, in some cases, only input signal just can control the adjustment of the associated fluid flow in flow control assembly 615 and nuclear fission module 30.
With reference to Figure 14 and 15, as previously mentioned, operation flow control assembly 615 is to provide convertible fluids flow to selected of nuclear fission module 30.Nuclear fission module 30 is according to the alternative of the expectation value of the operational factor (such as, temperature) in nuclear fission module 30 and the actual value of the operational factor sensed in nuclear fission module 30.As current more detailed description, adjust to the fluid flow of nuclear fission module 30 to make the expectation value of the actual value of operational factor and operational factor basically identical.In order to realize this result, moving bridge device 640a and 640b by actuating simultaneously and the bridge 620 belonging to balladeur train subassembly 630 is advanced along track 660a and 660b.Along with bridge 620 is advanced along track 660a and 660b, bridge 620 is advanced below reactor core lower supporting plate 360.More fully describe as current, the actual value of operational factor that bridge 620 finally senses according to the sensor 750 in nuclear fission module 30 and the expectation value of the operational factor of nuclear fission module 30 relatively make on it advance and stop at below reactor core lower supporting plate 360 precalculated position.The startup of advancing and the scope of moving bridge device 640a and 640b as by controller 720 or 740, can be controlled by suitable controller.About this respect, the position of selected according to multiple nuclear fission module 30 is stopped advancing of bridge 620 by controller 720 or 740.As described above, whether the nuclear fission module 30 that adjust can be selected according to basically identical between the expectation value of the operational factor of the actual value of the operational factor sensed at sensor 750 and nuclear fission module 30.Then, selected one of multiple hexagonal socket wrench 630 is made to move vertically upward matingly to engage with sexangle first joint 480.After tubular key 630 engages with the first joint 480, rotating shaft 700 is rotated, to make tubular key 630 rotate.It is that aforementioned lead screw device 670, first motor 710 by being coupled with controller 720 or 740 or the second motor 730 realize that rotating shaft 700 is rotated.
With reference to Fig. 7,8,8A, 8B, 8C, 8D, 8E, 9,10,11,12,13,14,15,16,17,18 and 19, after engaging with the first joint 480, tubular key 630 along the rotation of first direction make first or outer tube 450 rotate along identical first direction.Along with outer tube 450 rotates, owing to belonging to the first joint 480 of outer tube 450 and belonging to the engagement of the second joint 560 of inner sleeve 530, outer tube 450 can rise along the outside of inner sleeve 530 axially slidably.Along with outer tube 450 is along inner sleeve 530 upward sliding, first pore zone 460 of outer tube 450 will cut out gradually, cover, block, or otherwise the second hole 550 of blocking inner sleeve 530, and the second pore zone 540 of inner sleeve 530 will cut out simultaneously gradually, covers, block, or otherwise the first hole 470 of blocking outer tube 450.Close gradually, cover, block, or otherwise blocking the first hole 470 and the second hole 550 reduce the flow of the cooling medium by the first hole 470 and the second hole 550 changeably.In this case, in order to allow cooling medium flow through completely, the second hole 550 and the first hole 470 may be aim in the past.Alternately, in order to allow cooling medium part flow through, the second hole 550 and the first hole 470 may be that part is aimed in the past.
Referring again to Fig. 7,8,8A, 8B, 8C, 8D, 8E, 9,10,11,12,13,14,15,16,17,18 and 19, after engaging with the first joint 480, tubular key 630 along the rotation of the second direction contrary with first direction make first or outer tube 450 rotate along second direction.Along with outer tube 450 rotates, owing to belonging to the first joint 480 of outer tube 450 and belonging to the engagement of the second joint 560 of inner sleeve 530, outer tube 450 can decline along the outside of inner sleeve 530 axially slidably.Along with outer tube 450 is along inner sleeve 530 slide downward, first pore zone 460 of outer tube 450 by open gradually, open, disclose and otherwise the second hole 550 of dredging inner sleeve 530, and the second pore zone 540 of inner sleeve 530 will be opened gradually simultaneously, open, disclose and otherwise the first hole 470 of dredging outer tube 450.Open gradually, open, disclose and otherwise dredging the first hole 470 and the second hole 550 increase the flow of the cooling medium by the first hole 470 and the second hole 550 changeably.In this case, in order to limit or not allow cooling medium to flow through, the second hole 550 and the first hole 470 may be out-of-alignment in the past.Alternately, in order to part restriction or part do not allow cooling medium to flow through, the second hole 550 and the first hole 470 may be that part is out-of-alignment in the past.
Therefore, the use comprising the flow control assembly 615 of flow regulation subassembly 430 and balladeur train subassembly 610 one by one module (that is, one by one fuel assembly ground) achieve variable coolant stream.This makes it possible to be distributed across reactor core 20 ground according to the position of combustion wave 290 in reactor core 20 or non-uniform temperature and changes cooling medium stream.
exemplary methods
The exemplary methods that the one exemplary embodiment of present description and fission-type reactor and flow control assembly is associated.
With reference to Figure 20 A-20S, they provide the exemplary methods running fission-type reactor.
Forward now Figure 20 A to, run a kind of exemplary methods 760 of fission-type reactor from square 770.In square 780, the method is included on the position relative to nuclear fission module and produces the row ripple that burns at least partially.In square 790, respond the position relative to nuclear fission module, operation flow control assembly is to regulate the flow of fluid.The method is terminated in square 800.
In Figure 20 B, run a kind of exemplary methods 810 of fission-type reactor from square 820.In square 830, the position relative to nuclear fission module produces the row ripple that burns at least partially.In square 840, respond the position relative to nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.In square 850, operation flow regulation subassembly.The method is terminated in square 860.
In Figure 20 C, run the another kind of exemplary methods 870 of fission-type reactor from square 880.In square 890, the position relative to nuclear fission module produces the row ripple that burns at least partially.In square 900, respond the position relative to nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.Flow regulation subassembly is operated in square 910.In square 920, operate flow regulation subassembly according to the operational factor be associated with nuclear fission module.The method is terminated in square 930.
In Figure 20 D, run the further exemplary methods 940 of fission-type reactor from square 950.In square 960, the position relative to nuclear fission module produces the row ripple that burns at least partially.In square 970, respond the position relative to nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.Flow regulation subassembly is operated in square 980.In square 990, respond the operational factor be associated with nuclear fission module and adjust flow regulation subassembly.The method is terminated in square 1000.
In Figure 20 E, run the another kind of exemplary methods 1010 of fission-type reactor from square 1020.In square 1030, the position relative to nuclear fission module produces the row ripple that burns at least partially.In square 1040, respond the position relative to nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.Flow regulation subassembly is operated in square 1050.In square 1060, reconfigure flow regulation subassembly according to the predetermined input of flow regulation subassembly.The method is terminated in square 1070.
In Figure 20 F, run another exemplary methods 1080 of fission-type reactor from square 1090.In square 1100, the position relative to nuclear fission module produces the row ripple that burns at least partially.In square 1110, respond the position relative to nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.Flow regulation subassembly is operated in square 1120.In square 1130, realize controlled flow resistance.The method is terminated in square 1140.
In Figure 20 G, run a kind of exemplary methods 1150 of fission-type reactor from square 1160.In square 1170, the position relative to nuclear fission module produces the row ripple that burns at least partially.In square 1180, respond the position relative to nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.Flow regulation subassembly is operated in square 1190.In square 1200, inserted by the second sleeve pipe in the first sleeve pipe, first set pipe has the first hole, and the second sleeve pipe has the second hole can aimed at the first hole.The method is terminated in square 1210.
In Figure 20 H, run the another kind of exemplary methods 1220 of fission-type reactor from square 1230.In square 1240, the position relative to nuclear fission module produces the row ripple that burns at least partially.In square 1250, respond the position relative to nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.Flow regulation subassembly is operated in square 1260.In square 1270, operate the balladeur train subassembly be coupled with flow regulation subassembly.The method is terminated in square 1280.
In Figure 20 I, run the other exemplary methods 1290 of fission-type reactor from square 1300.In square 1310, the position relative to nuclear fission module produces the row ripple that burns at least partially.In square 1320, respond the position relative to nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.Flow regulation subassembly is operated in square 1330.In square 1340, temperature sensor is coupled with nuclear fission module and flow regulation subassembly.The method is terminated in square 1350.
In Figure 20 J, run the further exemplary methods 1360 of fission-type reactor from square 1370.In square 1380, the position relative to nuclear fission module produces the row ripple that burns at least partially.In square 1390, respond the position relative to nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.In square 1400, by arriving the time operation flow control assembly relative to the position of the position of nuclear fission module according to combustion wave, respond the flow of the position control fluid of the position relative to nuclear fission module.The method is terminated in square 1410.
In Figure 20 K, run another exemplary methods 1420 of fission-type reactor from square 1430.In square 1440, the position relative to nuclear fission module produces the row ripple that burns at least partially.In square 1450, respond the position relative to nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.In square 1460, by leaving the time operation flow control assembly of the position relative to nuclear fission module according to combustion wave, respond the flow of the position control fluid relative to nuclear fission module.The method is terminated in square 1470.
In Figure 20 L, run the another kind of exemplary methods 1480 of fission-type reactor from square 1490.In square 1500, the position relative to nuclear fission module produces the row ripple that burns at least partially.In square 1510, respond the position relative to nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.In square 1520, by according to the close time operation flow control assembly relative to the position of nuclear fission module of combustion wave, respond the flow of the position control fluid relative to nuclear fission module.The method is terminated in square 1530.
In Figure 20 M, run a kind of exemplary methods 1540 of fission-type reactor from square 1550.In square 1560, the position relative to nuclear fission module produces the row ripple that burns at least partially.In square 1570, respond the position relative to nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.In square 1580, according to the flow of the width control system fluid of combustion wave.The method is terminated in square 1590.
In Figure 20 N, run a kind of exemplary methods 1600 of fission-type reactor from square 1610.In square 1620, the position relative to nuclear fission module produces the row ripple that burns at least partially.In square 1630, respond the position relative to nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.In square 1640, by controlling the flow of fluid according to the rate of heat production operation flow control assembly in nuclear fission module.The method is terminated in square 1650.
In Figure 20 O, run a kind of exemplary methods 1660 of fission-type reactor from square 1670.In square 1680, the position relative to nuclear fission module produces the row ripple that burns at least partially.In square 1690, respond the position relative to nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.In square 1700, by controlling the flow of fluid according to the temperature operation flow control assembly in nuclear fission module.The method is terminated in square 1710.
In Figure 20 P, run a kind of exemplary methods 1720 of fission-type reactor from square 1730.In square 1740, the position relative to nuclear fission module produces the row ripple that burns at least partially.In square 1750, respond the position relative to nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.In square 1760, by controlling the flow of fluid according to the neutron flux operation flow control assembly in nuclear fission module.The method is terminated in square 1770.
In Figure 20 Q, run a kind of exemplary methods 1780 of fission-type reactor from square 1790.In square 1800, the position relative to nuclear fission module produces the row ripple that burns at least partially.In square 1810, respond the position relative to nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.In square 1820, relative to the position of fission fuel assemblies producing the row ripple of burning at least partially.The method is terminated in square 1830.
In Figure 20 R, run a kind of exemplary methods 1840 of fission-type reactor from square 1850.In square 1860, the position relative to nuclear fission module produces the row ripple that burns at least partially.In square 1870, respond the position relative to nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.In square 1880, relative to the position of fertile nuclei regeneration module producing the row ripple that burns at least partially.The method is terminated in square 1890.
In Figure 20 S, run a kind of exemplary methods 1900 of fission-type reactor from square 1910.In square 1920, the position relative to nuclear fission module produces the row ripple that burns at least partially.In square 1930, respond the position relative to nuclear fission module, the flow control assembly that operation is coupled with nuclear fission module is to regulate the flow of fluid.In square 1940, the position relative to neutron relfector assembly produces the row ripple that burns at least partially.The method is terminated in square 1950.
With reference to Figure 21 A-21H, they provide the exemplary methods that assembling is used in the flow control assembly in fission-type reactor.
Forward now Figure 21 A to, assembling is used in a kind of exemplary methods 1960 of the flow control assembly in fission-type reactor from square 1970.Flow regulation subassembly is received in square 1980.The method is terminated in square 1990.
In Figure 21 B, assembling is used in the another kind of exemplary methods 2000 of the flow control assembly in fission-type reactor from square 2010.Balladeur train subassembly is received in square 2020.The method is terminated in square 2030.
In Figure 21 C, assembling is used in the another kind of exemplary methods 2040 of the flow control assembly in fission-type reactor from square 2050.Flow regulation subassembly is received in square 2060.First sleeve pipe with the first hole is received in square 2070.In square 2080, inserted by the second sleeve pipe in the first sleeve pipe, the second sleeve pipe has the second hole can aimed at the first hole, and the first sleeve pipe is configured to rotatable, aims at the second hole to be rotated in the first hole.In square 2090, balladeur train subassembly is coupled with flow regulation subassembly.The method is terminated in square 2100.
In Figure 21 D, assembling is used in another exemplary methods 2110 of the flow control assembly in fission-type reactor from square 2120.Flow regulation subassembly is received in square 2130.First sleeve pipe with the first hole is received in square 2140.In square 2150, inserted by the second sleeve pipe in the first sleeve pipe, the second sleeve pipe has the second hole can aimed at the first hole.In square 2160, balladeur train subassembly is coupled with flow regulation subassembly.In square 2170, balladeur train subassembly is coupled with flow regulation subassembly, so that flow regulation subassembly is sent to fuel assembly by balladeur train subassembly.The method is terminated in square 2180.
In Figure 21 E, assembling is used in the further exemplary methods 2190 of the flow control assembly in fission-type reactor from square 2200.Flow regulation subassembly is received in square 2210.First sleeve pipe with the first hole is received in square 2220.In square 2230, inserted by the second sleeve pipe in the first sleeve pipe, the second sleeve pipe has the second hole can aimed at the first hole.In square 2240, balladeur train subassembly is coupled with flow regulation subassembly.In square 2250, balladeur train subassembly is coupled with flow regulation subassembly, to drive balladeur train subassembly by lead screw device.The method is terminated in square 2260.
In Figure 21 F, assembling is used in a kind of exemplary methods 2270 of the flow control assembly in fission-type reactor from square 2280.Flow regulation subassembly is received in square 2290.First sleeve pipe with the first hole is received in square 2300.In square 2310, inserted by the second sleeve pipe in the first sleeve pipe, the second sleeve pipe has the second hole can aimed at the first hole, and the first sleeve pipe is configured to rotatable, aims at the second hole to be rotated in the first hole.In square 2320, balladeur train subassembly is coupled with flow regulation subassembly.In square 2330, coupling balladeur train subassembly, to drive balladeur train subassembly by reversible electric machine device.The method is terminated in square 2340.
In Figure 21 G, assembling is used in a kind of exemplary methods 2350 of the flow control assembly in fission-type reactor from square 2360.Flow regulation subassembly is received in square 2370.First sleeve pipe with the first hole is received in square 2380.In square 2390, inserted by the second sleeve pipe in the first sleeve pipe, the second sleeve pipe has the second hole can aimed at the first hole, and the first sleeve pipe is configured to rotatable, aims at the second hole to be rotated in the first hole.In square 2400, balladeur train subassembly is coupled with flow regulation subassembly.In square 2410, coupling balladeur train subassembly, to control balladeur train subassembly at least partly by the transmitting set-acceptor device making reversible electric machine device operate.The method is terminated in square 2415.
In Figure 21 H, assembling is used in a kind of exemplary methods 2420 of the flow control assembly in fission-type reactor from square 2430.Flow regulation subassembly is received in square 2440.First sleeve pipe with the first hole is received in square 2450.In square 2460, inserted by the second sleeve pipe in the first sleeve pipe, the second sleeve pipe has the second hole can aimed at the first hole, and the first sleeve pipe is configured to rotatable, aims at the second hole to be rotated in the first hole.In square 2470, balladeur train subassembly is coupled with flow regulation subassembly.In square 2480, coupling balladeur train subassembly, to control balladeur train subassembly at least partly by the fiber optic emitter-acceptor device making reversible electric machine device operate.The method is terminated in square 2490.
Those skilled in the art will appreciate that parts as herein described (such as, operation), equipment, object and the discussion with them are used as the example of clarification concept, it is contemplated that out various configuration modification.Therefore, as used herein, the specific examples of displaying and adjoint discussion are intended to the more general category representing them.In general, the use of any specific examples is all intended to the classification representing it, and particular elements (such as, operate), equipment and object do not comprise not being considered as limiting property.
In addition, those skilled in the art can understand, aforesaid particular exemplary process, equipment and/or technology represent as other in the claims submitted to and/or in the application like that local herein, in more general process, equipment and/or technology that other place of this paper is told about.
Although shown and described the particular aspects of current topic as herein described, but for a person skilled in the art, obviously, can according to instruction herein, do not depart from theme as herein described and more broad aspect make and change and amendment, therefore, appended claims by as within the true spirit and scope of theme as herein described change and revise all be included in it scope within.Those skilled in the art should be understood that, in general, with in this article, especially appended claims is used in (such as, the major part of appended claims) in term be generally intended to as open to the outside world term (such as, gerund term " comprises " and is construed as gerund and " includes but not limited to ", and term " has " and is construed as " at least having ", verb term " comprise " be construed as verb and " include but not limited to ").Those skilled in the art it is also to be understood that, if having a mind to represent the claim recitation item of introducing of specific quantity, then will clearly enumerate such intention in the claims, and when shortage such enumerate, then there is not such intention.Such as, in order to help people to understand, following appended claims may comprise the introductory phrase " at least one " of use and " one or more " introduce claim recitation item.But, even if same claim comprises introductory phrase " one or more " or " at least one " and picture " " or " one " (such as, " one " and/or " one " should be understood to the meaning of " at least one " or " one or more " usually) such indefinite article, the use of such phrase not should be understood to yet imply by indefinite article " " or " one " introduce claim recitation item by comprise any specific rights introducing claim recitation item like this require to be limited in only comprise such listed item claim on, for the use of the definite article for introducing claim recitation item, this sets up equally.In addition, even if clearly list the claim recitation item of introducing of specific quantity, those skilled in the art also should be realized that, enumerating so usually should be understood at least there is cited quantity the meaning (such as, when there is no other qualifier, only enumerate " two listed item " and usually mean at least two listed item, or two or more listed item).And, be similar to those situations of the usage of " A, B and C etc. at least one " in use under, in general, such usage is intended to meaning that those skilled in the art understands this usage uses (such as, " to have the system of at least one of A, B and C " and will include but not limited to only have A, only there is B, only there is C, together there is A and B, together there is A and C, together there is B and C, and/or there is the system of A, B and C etc. together).Be similar to those situations of the usage of " A, B or C etc. at least one " in use under, in general, such usage is intended to meaning that those skilled in the art understands this usage uses (such as, " there is the system of at least one of A, B or C " and will include but not limited to only there is A, only there is B, only there is C, together there is A and B, together there is A and C, together there is B and C, and/or there is the system of A, B and C etc. together).Those skilled in the art it is also to be understood that, usually, no matter in description, claims or accompanying drawing, occur that the separation word of two or more alternative projects and/or phrase should be understood to have and comprise one of these projects, any one of these projects, or the possibility of two projects, unless context indicates otherwise.Such as, phrase " A or B " is usually understood as and comprises " A ", the possibility of " B " or " A and B ".
About appended claims, those skilled in the art can understand, operation cited herein generally can perform by any order.In addition, although various operating process displays in order, should be understood that various operation can perform by other order different from illustrated order, or can perform simultaneously.The example of alternative like this sequence can comprise overlap, interlocks, blocks, resets, increases progressively, prepares, supplements, simultaneously, oppositely or other derivative sequence, unless context indicates otherwise.And, as " right ... responsive ", " with ... about " or the such term of other past tense adjective be generally not intended to repel so derivative, unless context indicates otherwise.
Therefore, the fission-type reactor that provides, flow control assembly, its method and flow control assembly system.
Although disclosed herein is various aspect and embodiment, other side and embodiment are apparent for a person skilled in the art.Such as, can replace flow regulation subassembly with horizontally disposed pore plate, pore plate has multiple pore passed.Multiple corresponding of can activate catch and pore respectively can be associated, these catch can be closed gradually and open pore, to regulate or to adjust to the flow of the cooling medium of nuclear fission module.
In addition, can understand from instruction herein, different from the equipment be disclosed in above-cited existing patent, the flow of flow control assembly of the present disclosure and system dynamically alter, avoid and with accurate, the dependence that neutron brings out growth property is set to the difference of the structured material controlling fluid flow, and if if required, dynamically can change during reactor operation.
In addition, various aspect disclosed herein and embodiment are used for illustrative object, and are not intended to limit the scope of the invention, and true scope of the present invention and spirit are pointed out by following claims.
Claims (56)
1. a fission-type reactor, comprises:
A () nuclear fission module, is configured to have on the position relative to described nuclear fission module the row ripple that burns at least partially; And
B () flow control assembly, is configured to be coupled with described nuclear fission module, and be configured to respond the flow being in and regulating fluid relative to the burning row ripple on the position of described nuclear fission module,
Wherein said flow control assembly comprises flow regulation subassembly, and
Wherein said flow regulation subassembly comprises the first sleeve pipe and can insert the second sleeve pipe in described first sleeve pipe, described first set pipe have the first hole and described second sleeve pipe have can with second hole aimed at least partially in described first hole.
2. fission-type reactor as claimed in claim 1, wherein said flow regulation subassembly is configured to respond the operational factor be associated with described nuclear fission module and runs.
3. fission-type reactor as claimed in claim 2, the operational factor be wherein associated with described nuclear fission module is the Current Temperatures in described nuclear fission module.
4. fission-type reactor as claimed in claim 2, the operational factor be wherein associated with described nuclear fission module is the former temperature in described nuclear fission module.
5. fission-type reactor as claimed in claim 2, the operational factor be wherein associated with described nuclear fission module is the neutron flux in described nuclear fission module.
6. fission-type reactor as claimed in claim 2, the operational factor be wherein associated with described nuclear fission module is the neutron fluence in described nuclear fission module.
7. fission-type reactor as claimed in claim 2, the operational factor be wherein associated with described nuclear fission module is the characteristic isotope in described nuclear fission module.
8. fission-type reactor as claimed in claim 2, the operational factor be wherein associated with described nuclear fission module is the pressure in described nuclear fission module.
9. fission-type reactor as claimed in claim 2, the operational factor be wherein associated with described nuclear fission module is the rate of flow of fluid in described nuclear fission module.
10. fission-type reactor as claimed in claim 1, wherein said flow regulation subassembly is configured to respond the operational factor be associated with described nuclear fission module and adjusts.
11. fission-type reactors as claimed in claim 10, the adjustment wherein responding operational factor is determined by FEEDBACK CONTROL.
12. fission-type reactors as claimed in claim 10, the adjustment wherein responding operational factor is determined by operating personnel.
13. fission-type reactors as claimed in claim 10, the adjustment wherein responding operational factor is determined by computer based algorithm.
14. fission-type reactors as claimed in claim 10, the adjustment wherein responding operational factor is determined by automatic control system.
15. fission-type reactors as claimed in claim 10, the adjustment wherein responding operational factor is determined by the change of decay heat.
16. fission-type reactors as claimed in claim 1, wherein said flow regulation subassembly can reconfigure according to the predetermined input of described flow regulation subassembly.
17. fission-type reactors as claimed in claim 16, the predetermined input of wherein said flow regulation subassembly is the signal of response temperature sensor.
18. fission-type reactors as claimed in claim 16, the predetermined input of wherein said flow regulation subassembly is the signal produced by reactor control system.
19. fission-type reactors as claimed in claim 16, the predetermined input of wherein said flow regulation subassembly is the signal of fluid-responsive flowmeter.
20. fission-type reactors as claimed in claim 16, the predetermined input of wherein said flow regulation subassembly is the signal of response neutron-flux detector.
21. fission-type reactors as claimed in claim 1, wherein said flow regulation subassembly has controllable flow gap.
22. fission-type reactors as claimed in claim 1, wherein said flow regulation subassembly is configured to realize controlled flow resistance.
23. fission-type reactors as claimed in claim 1, wherein said flow control assembly comprises the balladeur train subassembly being configured to be coupled with described flow regulation subassembly further.
24. fission-type reactors as claimed in claim 1, comprise the temperature sensor being configured to be coupled with described nuclear fission module and described flow regulation subassembly further.
25. fission-type reactors as claimed in claim 1, wherein said flow control assembly is configured to according to the flow of combustion wave arrival relative to the time controling fluid of the position of nuclear fission module.
26. fission-type reactors as claimed in claim 1, wherein said flow control assembly is configured to the flow of the time controling fluid leaving the position relative to nuclear fission module according to combustion wave.
27. fission-type reactors as claimed in claim 1, wherein said flow control assembly is configured to according to combustion wave close to the flow relative to the time controling fluid of the position of nuclear fission module.
28. fission-type reactors as claimed in claim 1, wherein said flow control assembly is configured to the flow of the width control system fluid according to combustion wave.
29. fission-type reactors as claimed in claim 1, wherein said flow control assembly is configured to the flow controlling fluid according to the rate of heat production in described nuclear fission module.
30. fission-type reactors as claimed in claim 1, wherein said flow control assembly is configured to the flow according to the temperature control fluid in described nuclear fission module.
31. fission-type reactors as claimed in claim 1, wherein said flow control assembly is configured to the flow controlling fluid according to the neutron flux in described nuclear fission module.
32. fission-type reactors as claimed in claim 1,
A () wherein said nuclear fission module can have temperature correlation reactions change; And
B () wherein said flow control assembly is configured to control the temperature correlation reactions change in described nuclear fission module at least partly.
33. fission-type reactors as claimed in claim 1, wherein said nuclear fission module comprises fission fuel assemblies.
34. fission-type reactors as claimed in claim 1, wherein said nuclear fission module comprises can fertile nuclei regeneration module.
35. fission-type reactors as claimed in claim 1, wherein said nuclear fission module comprises neutron relfector assembly.
36. 1 kinds of fission-type reactors, comprise:
A () heating fission fuel assemblies, is configured to have on the position relative to described fission fuel assemblies the row ripple that burns at least partially; And
B () flow control assembly, is configured to be coupled with described fission fuel assemblies, and can respond the flow being in and regulating fluid stream relative to the burning row ripple on the position of described fission fuel assemblies,
Wherein said flow control assembly comprises the adjustable flow adjustment subassembly being configured to be arranged in fluid stream, and
Wherein said flow control assembly comprises the balladeur train subassembly being configured to regulate subassembly to be coupled with described adjustable flow.
37. fission-type reactors as claimed in claim 36, wherein said adjustable flow regulates subassembly to be configured to respond the operational factor be associated with described fission fuel assemblies and runs.
38. fission-type reactors as claimed in claim 37, the operational factor be wherein associated with described fission fuel assemblies is the Current Temperatures in described fission fuel assemblies.
39. fission-type reactors as claimed in claim 37, the operational factor be wherein associated with described fission fuel assemblies is the neutron fluence in described fission fuel assemblies.
40. fission-type reactors as claimed in claim 37, the operational factor be wherein associated with described fission fuel assemblies is the characteristic isotope in described fission fuel assemblies.
41. fission-type reactors as claimed in claim 37, the operational factor be wherein associated with described fission fuel assemblies is the pressure in described fission fuel assemblies.
42. fission-type reactors as claimed in claim 37, the operational factor be wherein associated with described nuclear fission module is the rate of flow of fluid in described fission fuel assemblies.
43. fission-type reactors as claimed in claim 36, wherein said adjustable flow regulates subassembly the predetermined input of subassembly can be regulated to reconfigure according to described adjustable flow.
44. fission-type reactors as claimed in claim 43, the predetermined input of wherein said adjustable flow adjustment subassembly is the signal of response temperature sensor.
45. fission-type reactors as claimed in claim 43, wherein said adjustable flow regulates the predetermined input of subassembly to be the signal responding reactor control system.
46. fission-type reactors as claimed in claim 43, the predetermined input of wherein said adjustable flow adjustment subassembly is the signal of fluid-responsive flowmeter.
47. fission-type reactors as claimed in claim 43, wherein said adjustable flow regulates the predetermined input of subassembly to be the signal that neutron-flux detector produces.
48. fission-type reactors as claimed in claim 36, wherein said adjustable flow regulates subassembly to have controllable flow gap.
49. fission-type reactors as claimed in claim 36, wherein said adjustable flow regulates subassembly to be configured to realize controlled flow resistance.
50. fission-type reactors as claimed in claim 36, wherein said flow control assembly is configured to according to the flow of combustion wave arrival relative to the time controling fluid of the position of described fission fuel assemblies.
51. fission-type reactors as claimed in claim 36, wherein said flow control assembly is configured to the flow of the time controling fluid stream leaving the position relative to described fission fuel assemblies according to combustion wave.
52. fission-type reactors as claimed in claim 36, wherein said flow control assembly is configured to according to combustion wave close to the flow relative to the time controling fluid of the position of described fission fuel assemblies.
53. fission-type reactors as claimed in claim 36, wherein said flow control assembly is configured to the flow of the width control system fluid stream according to combustion wave.
54. fission-type reactors as claimed in claim 36, wherein said flow control assembly is configured to the flow controlling fluid stream according to the rate of heat production in described fuel assembly.
55. fission-type reactors as claimed in claim 36, wherein said flow control assembly is configured to the flow according to the temperature control fluid stream in described fuel assembly.
56. fission-type reactors as claimed in claim 36, wherein said flow control assembly is configured to the flow controlling fluid stream according to the neutron flux in described fuel assembly.
Applications Claiming Priority (9)
| Application Number | Priority Date | Filing Date | Title |
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| US12/386,495 US8320513B2 (en) | 2009-04-16 | 2009-04-16 | Nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system |
| US12/386,495 | 2009-04-16 | ||
| US12/460,157 | 2009-07-13 | ||
| US12/460,157 US8369474B2 (en) | 2009-04-16 | 2009-07-13 | Nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system |
| US12/460,159 US20100266087A1 (en) | 2009-04-16 | 2009-07-13 | Nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system |
| US12/460,160 | 2009-07-13 | ||
| US12/460,160 US20100266088A1 (en) | 2009-04-16 | 2009-07-13 | Nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system |
| US12/460,159 | 2009-07-13 | ||
| PCT/US2010/001129 WO2010141048A1 (en) | 2009-04-16 | 2010-04-16 | A nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system |
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| CN102460594A CN102460594A (en) | 2012-05-16 |
| CN102460594B true CN102460594B (en) | 2015-02-18 |
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| CN201080027018.0A Active CN102460595B (en) | 2009-04-16 | 2010-04-16 | Nuclear fission reactor having flow control assembly |
| CN201080027017.6A Active CN102460594B (en) | 2009-04-16 | 2010-04-16 | A nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system |
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| CN201080027018.0A Active CN102460595B (en) | 2009-04-16 | 2010-04-16 | Nuclear fission reactor having flow control assembly |
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| CN (4) | CN102804283B (en) |
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| CN105427898B (en) * | 2015-12-09 | 2017-09-12 | 中国原子能科学研究院 | A kind of travelling-wave-type of multi partition pattern burns long core life |
| CN112185598B (en) * | 2020-09-30 | 2022-02-01 | 中国核动力研究设计院 | Stacking type flow distribution device and distribution structure |
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| CN102460591B (en) | 2014-09-24 |
| RU2531359C2 (en) | 2014-10-20 |
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| WO2010132084A2 (en) | 2010-11-18 |
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