CN102460595B - Nuclear fission reactor having flow control assembly - Google Patents

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

There is the fission-type reactor of flow control assembly

Cross

The application relate to following listed application (" related application ") and require from following listed application, to obtain the earliest can with the rights and interests of live application day (for example, what require non-temporary patent application can use priority date the earliest, or require temporary patent application, and any and all parents of related application, Zu Fudai, great grandfather's generation etc. the rights and interests of application based on 35USC § 119 (e)).All themes of the applications such as any and all parents of related application and related application, Zu Fudai, great grandfather's generation can be not inconsistent with theme herein with such theme degree be incorporated herein by reference.

related application

According to the non-legal requirements of United States Patent (USP) 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, Ashok Odedra, Clarence T.Tegreene, Thomas Allan Weaver, Charles Whitmer, Victoria Y.H.Wood, Lowell L.Wood, Jr. and George B.Zimmerman, be " A NUCLEAR FISSION REACTOR, FLOW CONTROL ASSEMBLY, METHODS THEREFOR 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 current while pending trial of this application, or give the application of current while co-pending application with the rights and interests of the applying date.

According to the non-legal requirements of United States Patent (USP) 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, Ashok Odedra, Clarence T.Tegreene, Thomas Allan Weaver, Charles Whitmer, Victoria Y.H.Wood, Lowell L.Wood, Jr. and George B.Zimmerman, be " A NUCLEAR FISSION REACTOR, FLOW CONTROL ASSEMBLY, METHODS THEREFOR 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 current while pending trial of this application, or give the application of current while co-pending application with the rights and interests of the applying date.

According to the non-legal requirements of United States Patent (USP) 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, Ashok Odedra, Clarence T.Tegreene, Thomas Allan Weaver, Charles Whitmer, Victoria Y.H.Wood, Lowell L.Wood, Jr. and George B.Zimmerman, be " A NUCLEAR FISSION REACTOR, FLOW CONTROL ASSEMBLY, METHODS THEREFOR 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 current while pending trial of this application, or give the application of current while co-pending application with the rights and interests of the applying date.

According to the non-legal requirements of United States Patent (USP) 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, Ashok Odedra, Clarence T.Tegreene, Thomas Allan Weaver, Charles Whitmer, Victoria Y.H.Wood and Lowell L.Wood, Jr., be " A NUCLEAR FISSION REACTOR with denomination of invention, FLOW CONTROL ASSEMBLY, METHODS THEREFOR AND A FLOW 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 current while pending trial of this application, or give the application of current while co-pending application with the rights and interests of the applying date.

It is that the computer program of USPTO requires patent applicant to quote sequence number and instruction application is continuation application or the bulletin of part continuation application that United States Patent (USP) trademark office (USPTO) has issued content.Details refers to the article that can find on http://www.uspto.gov/web/offices/com/sol/og/2003/week11/patbene .htm., Stephen G.Kunin, Benefit of Prior-Filed Application, USPTO Official Gazette March 18,2003.The applicant's entity (hereinafter referred to as " applicant ") provides in the above and as described in regulation, has required the specific of application of its right of priority to quote.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 input requirements, therefore the part that the application is designated as its parent application as mentioned above by the applicant continues, but should explicitly point out, such appointment must not be understood as except the theme of its parent application, the application whether comprise certain new theme any type annotation and/or admit.

Technical field

The structure that the application relates generally to involve the process of induced nuclear reaction and realizes such process, this structure comprises hole or the fluid control device on entrance, outlet or cooling duct, relates in particular to fission-type reactor, flow control assembly, its method and flow control assembly system.

Background technology

As everyone knows, in the fission-type reactor moving, the nucleic that the neutron of known energy is had thick atom quality absorbs.The compound nucleus producing resolves into the fission product and the 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.For example, kinetic energy is that the thermal neutron of 0.0253eV (electron-volt) can be used for making U-235 nuclear fission.Can not bring out fission as thorium-232 and uranium-238 that can breed nucleic, be the fast neutron of 1MeV (million-electron-volt) at least unless utilized kinetic energy.The total kinetic energy discharging from each fission event is about 200MeV.This kinetic energy finally changes into heat.

In nuclear reactor, above-mentioned fissible and/or can conventionally leave in the multiple tightly packed fuel assembly together that defines 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 increase the risk that fuel pellet may break and/or fuel rod may be bending.Fuel pellet breaks may be prior to the fuel-involucrum fault mechanism as fuel-involucrum mechanical interaction, and causes fission gas to discharge.Fission gas discharges and can in reactor core, produce higher than normal radiation level.Fuel rod bending may cause coolant flow channel to be blocked.

Do enough coolant flows to offer the trial of fuel assembly for nuclear reactor.On March 19th, 1985 issues and the United States Patent (USP) 4th of denomination of invention as " Device for Regulating the Flow of a Fluid (regulating the equipment of the flow of fluid) " taking the name of Jacky Rion, the equipment of a series of grids of the direction that comprises and change fluid stream vertical with fluid stream is disclosed for 505, No. 877.According to the patent of Rion, this equipment intends to be used in the direction of the cooling fluid circulating in the pedestal that is adjusted in the cooling nuclear reactor component of liquid metal.Being devoted to of this equipment, for given nominal flow rate and given downstream pressure, do not produce cavity and causes to constant pressure drop.

Issue and the United States Patent (USP) 5th of denomination of invention as " Nuclear Fuel Assembly Coolant Control (control of nuclear fuel assembly cooling medium) " taking the people's such as Neil G.Heppenstall name on November 19th, 1991,066, in No. 453, the another kind trial that enough coolant flows is offered to fuel assembly for nuclear reactor is disclosed.This patent discloses by the device of the flow of nuclear fuel assembly control cooling medium, and this device comprises the variable restrictor that can be in fuel assembly, be on the position in fuel assembly to cause that self neutron brings out the mode increasing and responds the device of neutron irradiation and be connected with variable restrictor with by neutron irradiation responding device to control cooling medium by the coupling arrangement of the flow of fuel assembly.Variable restrictor comprises many longitudinal alignment pipelines and has 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 gradually some pipelines by coupling arrangement length travel blocking device.

Issue and the United States Patent (USP) 5th of denomination of invention as " Nuclear Reactor Flow Control Method and Apparatus (nuclear reactor flow control methods and device) " taking the name of John P.Church on March 30th, 1993,198, in No. 185, another trial that enough coolant flows is offered to fuel assembly for nuclear reactor is disclosed.This patent seems to disclose the coolant flow distribution that makes mobile improving and do not make mobile deterioration under generation event conditions under normal condition.According to this patent, Universal casing shell surrounds fuel element.This Universal casing shell has the multiple holes that allow cooling medium pass through.Quantity and the big or small change of sleeve pipe ground to the hole in sleeve shell one by one, to increase the quantity of the cooling medium that flows to reactor core center fuel, and is reduced to the flow of peripheral fuel relatively.In addition,, according to this patent, change the quantity in hole and the size in hole and can meet the certain power shape that strides across reactor core.

Summary of the invention

According to an aspect of the present disclosure, a kind of fission-type reactor is provided, it comprises nuclear fission module, is configured to have at least a portion burning row ripple (traveling burn wave) on the position with respect to this nuclear fission module; And flow control assembly, be configured to this nuclear fission module coupling and be configured to response be in the flow that regulates fluid with respect to the locational burning row ripple of this nuclear fission module.

According to another aspect of the present disclosure, a kind of fission-type reactor is provided, it comprises heating nuclear fission fuel assembly, is configured to have at least a portion burning row ripple on the position with respect to this nuclear fission fuel assembly; And flow control assembly, be configured to this nuclear fission fuel assembly coupling and can respond be in the flow that regulates fluid stream with respect to the locational burning row ripple of this nuclear fission fuel assembly.

According to another aspect of the present disclosure, the flow control assembly that provides a kind of use to be expert in ripple fission-type reactor, it comprises flow regulation subassembly.

According to another aspect of the present disclosure, a kind of flow control assembly being used in fission-type reactor is provided, it comprises flow regulation subassembly, and this flow regulation subassembly comprises first sleeve pipe with the first hole; Be configured to insert the second sleeve pipe in the first sleeve pipe, the second sleeve pipe has the second hole that can aim at the first hole, and the first sleeve pipe is configured to rotatable, to the first hole is aimed at the second hole; And be configured to and the balladeur train subassembly of flow regulation subassembly coupling.

According to another aspect of the present disclosure, provide a kind of use to be expert in ripple fission-type reactor, be configured to the flow control assembly that is connected with fuel assembly, it comprises the adjustable flow that is configured to be arranged in fluid stream and regulates subassembly.

According to further aspect of the present disclosure, provide a kind of and be used in fission-type reactor, be configured to the flow control assembly that is connected with fuel assembly, it comprises the adjustable flow that is configured to be arranged in fluid stream and regulates subassembly, and this adjustable flow regulates subassembly to comprise first sleeve pipe with the first hole; And be configured to insert the second sleeve pipe in the first sleeve pipe, the second sleeve pipe has the second hole, the first hole can be aimed at the second hole gradually, thereby along with the first hole is aimed at the second hole gradually, the fluid stream of variable number flows through the first hole and the second hole, the first sleeve pipe is configured to can be with respect to the second sleeve pipe axial translation, to the second hole is aimed at the first hole.

According to other aspect of the present disclosure, provide a kind of and be 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 coupling to adjust the balladeur train subassembly of adjustable flow adjusting subassembly with adjustable flow.

According to another aspect of the present disclosure, provide a kind of and be used in fission-type reactor, can with the flow control assembly that is arranged to a selected coupling that is arranged in the multiple nuclear fission fuel assemblies in fission-type reactor, its adjustable flow that comprises the flow of adjusting the fluid stream of selected one that flows through multiple nuclear fission fuel assemblies regulates subassembly, and this adjustable flow regulates subassembly to comprise the outer tube with multiple the first holes; Insert the inner sleeve in outer tube, inner sleeve has multiple the second holes, variable flow district can be aimed to define with the second hole gradually in the first hole, thereby along with the first hole and the second hole aim to define variable flow district gradually, the fluid stream of variable number flows through the first hole and the second hole; And regulate subassembly coupling to adjust the balladeur train subassembly of adjustable flow adjusting subassembly with adjustable flow.

According to further aspect of the present disclosure, a kind of method of moving fission-type reactor is provided, it is included in and on the position with respect to nuclear fission module, produces at least a portion burning row ripple; And response is with respect to the position of nuclear fission module, operates with the flow control assembly of nuclear fission module coupling to regulate the flow of fluid.

According to another aspect of the present disclosure, a kind of method of assembling with the flow control assembly in ripple fission-type reactor of being expert at is provided, it comprises receives flow regulation subassembly.

According to another aspect of the present disclosure, a kind of method of assembling with the flow control assembly in ripple fission-type reactor of being expert at is provided, it comprises receives balladeur train subassembly.

According to another aspect of the present disclosure, a kind of method of assembling with the flow control assembly in ripple fission-type reactor of being expert at is provided, it comprises receives first sleeve pipe with the first hole; The second sleeve pipe is inserted in the first sleeve pipe, and the second sleeve pipe has the second hole that can aim at the first hole, and the first sleeve pipe is configured to rotatable, to the first hole axial translation is become to aim at the second hole; And by balladeur train subassembly and the coupling of flow regulation subassembly.

According to other aspect of the present disclosure, provide by the flow control assembly system of being expert in ripple fission-type reactor, it comprises flow regulation subassembly.

According to another aspect of the present disclosure, the flow control assembly being used in fission-type reactor system is provided, it comprises flow regulation subassembly, and this flow regulation subassembly comprises first sleeve pipe with the first hole; Be configured to insert the second sleeve pipe in the first sleeve pipe, the second sleeve pipe has the second hole that can aim at the first hole, and the first sleeve pipe is configured to rotatable, to the first hole axial translation is become to aim at the second hole; And be configured to and the balladeur train subassembly of flow regulation subassembly coupling.

According to another aspect of the present disclosure, provide a kind of and be used in fission-type reactor, be configured to the flow control assembly system that is connected with nuclear fission fuel assembly, it comprises the adjustable flow that is configured to be arranged in fluid stream and regulates subassembly.

According to another aspect of the present disclosure, provide a kind of and be used in fission-type reactor, can with the flow control assembly system of a selected coupling that is arranged in the multiple nuclear fission fuel assemblies in fission-type reactor, its adjustable flow that comprises the flow of controlling the fluid stream of selected one that flows through multiple nuclear fission fuel assemblies regulates subassembly, and this adjustable flow regulates subassembly to comprise the outer tube with multiple the first holes; Insert the inner sleeve in outer tube, inner sleeve has multiple the second holes, variable flow district can be aimed to define with the second hole gradually in the first hole, thereby along with the first hole and the second hole aim to define variable flow district gradually, the fluid stream of variable number flows through the first hole and the second hole; And regulate subassembly coupling to adjust the balladeur train subassembly of adjustable flow adjusting 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 that comprises 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 that can aim at the first hole, thereby along with the second hole is aimed at the first 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 the coupling of flow regulation subassembly to transmit and configure the balladeur train subassembly of flow regulation subassembly.

Except above, propose and described various other methods and/or equipment aspect for example, as the instruction of text (, claims and/or detailed description) and/or accompanying drawing in of the present disclosure.

Above a summary, therefore may comprise details simplification, summarize, comprise and/or omit; Therefore, those skilled in the art will recognize that, this summary is exemplary, and any restriction is carried out in plan anything but.Except above-mentioned exemplary aspect, embodiment and feature, by reference to accompanying drawing and following detailed description in detail, further aspect, embodiment and feature will become obvious.

Brief description of the drawings

Although this instructions using particularly point out and differently state theme of the present disclosure claims as conclusion, believe that the disclosure can better be understood from the following detailed description done by reference to the accompanying drawings.In addition, be used in the similar or identical items of same-sign ordinary representation in different accompanying drawings.

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 and the local vertical section that belong to the nuclear fuel rod of nuclear fission module represent;

Fig. 2 is the cross-sectional view with the hexagonal configuration fission-type reactor reactor core that is arranged in multiple hexagonal configuration nuclear fission modules wherein;

Fig. 3 is the cross-sectional view with the cylindrical shape reactor core that is arranged in multiple hexagonal configuration nuclear fission modules wherein;

Fig. 4 is the cross-sectional view of parallelepiped-shaped reactor core, and this reactor core has at least a portion burning row ripple that is arranged in multiple hexagonal configuration nuclear fission modules wherein and being included in and has on the position with respect to nuclear fission module width " x ";

Fig. 5 is the cross-sectional view of multiple adjacent hexagonal configuration nuclear fission modules, 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 configuration nuclear fission modules, 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 configuration nuclear fission modules, and except fuel rod, this nuclear fission module also has the many neutron relfector rods that are 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 of arranging around in it around;

Fig. 6 is the view intercepting along the profile line 6-6 of Fig. 5;

Fig. 7 be multiple adjacent nuclear fission modules and belong to flow control assembly and with the partial vertical sectional view of multiple flow regulation subassemblies of the coupling separately of nuclear fission module;

Fig. 8 is the perspective exploded view of flow regulation subassembly;

Fig. 8 A is the partial vertical sectional exploded view of flow regulation subassembly;

Fig. 8 B is the part sectioned view of opening configuration down-off adjusting subassembly that allows fluid to flow through completely;

Fig. 8 C is the part sectioned view of closing configuration down-off adjusting subassembly that stops fluid to flow through completely;

Fig. 8 D is the view intercepting along the profile line 8D-8D of Fig. 8 B, shows belong to flow regulation subassembly bottom anti-turn configuration with horizontal cross-section;

Fig. 8 E is the vertical cross section that for the sake of clarity part has been removed of flow regulation subassembly bottom, shows and can rotate freely joint;

Fig. 9 is with nuclear fission module coupling and is in the partial front figure of the flow regulation subassembly on the fully open position that allows fluid to flow to nuclear fission module;

Figure 10 is with nuclear fission module coupling and is in and prevents that fluid from flowing to the partial front figure of the flow regulation subassembly in the complete off-position of nuclear fission module;

Figure 11 is multiple adjacent nuclear fission modules and the vertical cross section with multiple flow regulation subassemblies of one of nuclear fission module coupling;

Figure 12 is multiple adjacent nuclear fission modules and the vertical cross section with multiple flow regulation subassemblies of the coupling separately of nuclear fission module, and this flow regulation subassembly is displayed on opening completely of allowing that convertible fluids flows through, position that part is closed or opened and closes completely;

Figure 13 is the skeleton view that for the sake of clarity part has been removed that belongs to the balladeur train subassembly of flow control assembly;

Figure 14 is multiple adjacent nuclear fission modules and the vertical cross section of the multiple sensors in separately that is arranged in nuclear fission module;

Figure 15 is the partial front figure that removed of for the sake of clarity part of multiple flow regulation subassemblies, multiple flow regulation subassemblies selected one by the engagement of one of multiple tubular keys of being rotarilyd actuate by lead screw device and axially driven by toothed gearing;

Figure 16 is the skeleton view that drives the optional person's of multiple tubular keys toothed gearing;

Figure 17 is the partial front figure that for the sake of clarity part has been removed by multiple flow regulation subassemblies of a selected engagement of multiple tubular keys, and tubular key is subject to the sealed electric-motor device control with controller or control module electric coupling at least partly;

Figure 18 is the partial front figure that for the sake of clarity part has been removed by multiple flow regulation subassemblies of a selected engagement of multiple tubular keys, and tubular key is subject to response can send the sealed electric-motor device control of the transmitting set-acceptor device that belongs to controller or control module of radiofrequency signal at least partly;

Figure 19 is by the partial front figure of multiple flow regulation subassemblies of a selected engagement of multiple tubular keys, and tubular key is subject at least partly can be by the fiber optic emitter-acceptor device control that belongs to control module of light beam transmitted signal;

Figure 20 A-20S is the process flow diagram of the exemplary methods of operation fission-type reactor; And

Figure 21 A-20H is the process flow diagram of the exemplary methods of assembling flow control subassembly.

Embodiment

In the following detailed description, with reference to forming its a part of accompanying drawing.In these accompanying drawings, the similar similar parts of symbol ordinary representation, unless context separately has regulation.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.Can not depart from herein the theme of showing spirit or scope utilize other embodiment, and can make other change.

In addition, for the purpose of clearly showing, the application has used pro forma generality title.But, should be understood that, these generality titles are for the object of showing, dissimilar theme can be discussed in whole application and (for example, can under process/operation title, describe equipment/structure and/or can be in discussion process/operation under structure/prelude; And/or the description of single topic can be crossed 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 is sometimes exemplified with being included in other different parts, or the different parts of parts different from other connection.Should be understood that the framework of describing is like this only exemplary, in fact, can realize many other frameworks of realizing identical function.From concept, effectively " contact " realize any arrangement of the parts of identical function, to realize desired function.Therefore, combine any two parts of realizing specific function herein and can regard " contact " mutually as, make independently to realize desired function with framework or intermediate member.Equally, so any two parts of contact also can be regarded mutual " being operably connected " or " operationally coupling " of realizing desired function as, and any two parts that can so contact also can be regarded mutual " can operational coupled " that realize desired function as.Special case that can operational coupled 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/parts in logic can interact.

In some cases, one or more parts may be called as " being configured to " in this article, and " can be configured to ", " can operate/operate ", " be applicable to/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/applicable to ", " can ", " can according to/according to " etc. generally can comprise active state parts, inactive state parts and/or waiting status parts, unless context separately has requirement.

About the disclosure, as previously mentioned, in many cases, for the each neutron absorbing, discharge a more than neutron, until fissionable atom core exhausts in fissilenuclide.This phenomenon is used in business nuclear reactor, to produce and continuous heat for generating electricity.

But, due to " peak " temperature being caused by the inhomogeneous Neutron flux distribution in reactor core (the instant heating channel peak factor), may there is the fire damage to reactor structural material.As well known in the art, neutron flux is defined by time per unit by the quantity of the neutron of unit area.This peak temperature is distributed and is caused by inhomogeneous control rod/fuel rod again.If peak temperature exceedes material limits, just may there is fire damage.In addition, operate in reactor in fast neutron spectrum may be designed to have be present in reactor core around can breed fuel " regeneration blanket " material.Such reactor will be tending towards making fuel reproduction become regeneration blanket material by neutron-absorbing.This has caused finishing along with reactor approaches fuel recycle, and the output power of reactor periphery increases.Start to make cooling medium to flow through peripheral assembly in reactor fuel circulation and can keep safe running temperature, and take into account during fuel recycle along with burnup increases the increase of output power occurring.

Due to fuel " burnup ", produce " reaction " (, variation of reactor capability).Burnup is defined as the energy fluence of the fuel generation of per unit mass conventionally, conventionally uses the unit of megawatt day per metric ton heavy metal (MWd/MTHM) or m. gigawatt (GW) sky per metric ton heavy metal (GWd/MTHM) to express.More particularly, " reactions change " is relevant with the relative capacity that reactor produces the neutron many or fewer than the exact amount that keeps critical chain reaction.The response of reactor conventionally characterize into make reactor power index increase or the time-derivative of the reactions change that reduces.

About this respect, the control rod of being made up of neutron absorber material is generally used for adjusting and controlling reacting condition.Make such control rod pass in and out back and forth reactor core, to control changeably neutron-absorbing in reactor core, therefore control neutron-flux level and reactivity.Neutron-flux level reduces near control rod, and may be higher in the region away from control rod.Therefore, neutron flux is inhomogeneous in whole reactor core.This has caused in those higher regions of neutron flux fuel burn-up higher.In addition, the those of ordinary skill in nuclear energy power generation field can understand, neutron flux and power density change and caused by many factors.May be may not be also principal element from control rod distance.For example, neutron flux does not nearby have significantly to decline on the reactor core border of control rod conventionally.These effects may cause again the overheated or peak temperature in those regions that neutron flux is higher.Such peak temperature may be because having changed the engineering properties of structure but not has been shortened as desired the operation life of the structure that stands such peak temperature.In addition, the proportional reactor capability density of product to neutron flux and fissionable fuel concentration is subject to core structural material to bear the capabilities limits of such peak temperature injury-freely.

Therefore,, with reference to Fig. 1, only as an example and without limitation, Fig. 1 shows the fission-type reactor that is referred to as 10, processes the concern of enumerating above.As below more fully described, reactor 10 can be row ripple fission-type reactor.Fission-type reactor 10 is created in the electric power that is transferred to power consumer on plurality of transmission lines (not shown).Reactor 10 can be alternatively for the test as determining the test of the impact of temperature on pile materials.

With reference to Fig. 1,1A, 1B and 2, reactor 10 comprises the fission-type reactor reactor core that is referred to as 20, and fission-type reactor reactor core 20 comprises multiple nuclear fission fuel assemblies, or also as alleged in this paper, 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 with the nuclear fission module 30 as cylindrical or spheroidal, more nuclear fission module 30 to be closely deposited in reactor core 20 together.Each nuclear fission module 30 comprises the many fuel rods 40 that generate heat due to above-mentioned fission chain reaction process.If necessary, can surround fuel rod 40 with fuel rod cylinder 43, to increase the structural rigidity of nuclear fission module 30 and isolate one by one nuclear fission module 30.Isolate one by one nuclear fission module 30 and avoided the horizontal cooling medium cross flow one between adjacent nuclear fission module 30.Avoid horizontal cooling medium cross flow one 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 below more fully described, isolate one by one nuclear fission module 30 and make to control to module one by one coolant flow.Control to separately, the coolant flow of preliminary election nuclear fission module 30 according to the uneven temperature distribution direct coolant flow in reactor core 20, effectively manages the coolant flow in reactor core 20 as substantially.Cylindrical shell 43 can comprise puts superincumbent annular shoulder 46 (referring to Fig. 7) by the fuel rod bundling.The in the situation that of exemplary sodium cooling reactor, at normal operation period, cooling medium can have about 5.5m ³/ s (, approximately 194 cubes of ft ³/ average specified volume flow rate s) and the average rated speed of about 2.3m/s (, about 7.55ft/s).Fuel rod 40 is adjacent one another are, defines therebetween and makes the coolant flow channel 47 (referring to Fig. 7) of cooling medium along the flows outside of fuel rod 40.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 known technology of the those of ordinary skill of power producer design field, still make fuel rod 40 keep in spaced relation along the pack-thread 50 (referring to Fig. 7) of the length spiral extension of every fuel rod 40.

With particular reference to Figure 1B, every fuel rod 40 has the end to end multiple fuel balls 60 that are 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 of just having mentioned above in fission process.Further substitute is that 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 be by from being made up of the oxide selecting the group that forming as follows substantially: 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 or unalloyed uranium as (but being not limited to) zirconium or thorium metal.Substitute as another, fuel ball 60 can mainly comprise the carbonide (UC of uranium _x) or the carbonide (ThC of thorium _x).For example, fuel ball 60 can be by from being made up of the carbonide selecting the group that forming as follows substantially: 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 be by from being made up of the nitride selecting the group that forming as follows substantially: 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 that surrounds hermetically fuel ball 60 in heaps can be the picture ZIRCOLOY of known anticorrosive and resistance to fracture ^tM(registered trademark of Westinghouse Electrical Corp. (Westinghouse Electric Corporation)) such suitable zircaloy.Cladding materials 70 also can be made up of other material as ferrito-martensite steel.

From Fig. 1, can the best see, reactor core 20 is disposed in reactor pressure vessel 80, to prevent that radioactive particle, gas or liquid from leaking into biosphere around from reactor core 20.Pressure vessel 80 can be steel, concrete or the other materials of suitable size and thickness, to reduce the risk of such radiation leakage and to support required pressure load.In addition, may there is the containment (not shown) of the part that surrounds hermetically reactor 10, to strengthen preventing that radioactive particle, gas or liquid from leaking into the guarantee in biosphere around 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) other such fluid.As another example, cooling medium can be liquid metal.Such liquid metal can be lead (Pi) alloy as lead-bismuth (Pb-Bi).And cooling medium can be the organic coolant as polyphenyl or fluorocarbon.In example 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.For example, have in the situation of 500 to 1, the 500 megawatt sodium cooling reactors that mix uranium-plutonium oxide fuel, can be from approximately 510 DEG C (in normal operation period reactor core outlet temperature, 950 °F) to approximately 550 DEG C (, 1,020 °F).On the other hand, during LOCA (coolant loss accident) or LOFTA (the of short duration forfeiture accident of flow), depend on reactor core design and running history, (fuel can peak temperature may reach approximately 600 DEG C, 1,110 °F) or higher.In addition, after LOCA and after LOFTA, the accumulation of the decay heat during situation and during reactor operation suspension may cause unacceptable heat built-up.Therefore, in some cases, the coolant flow that controls to reactor core 20 after normal operation situation and accident during situation is suitable.

In addition, the temperature curve in reactor core 20 is as the function of position and become.About this respect, the Temperature Distribution in reactor core 20 may be immediately following the power density space distribution in reactor core 20.As everyone knows, in the case of lacking around reactor core 20 suitable neutron relfector or neutron reproduction " blanket " around, near power density reactor core 20 centers is generally higher than near reactor core 20 power density around.Therefore, expect, around reactor core 20, near the coolant flow parameter of nuclear fission module 30 is by being less than near the coolant flow parameter of the nuclear fission module 30 reactor core 20 centers, especially in the time that the reactor core life-span has just started.Therefore, in this case, will there is no need provides identical or even coolant mass flow rate to each nuclear fission module 30.As detailed below, provide following technology: depend on position and the desirable reactor operation result of nuclear fission module 30 in reactor core 20, change to the coolant flow 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.Flow through intermediate heat exchanger 100 along the mobile cooling medium of coolant flow paths 95, flow in the pumping chamber 105 being associated with intermediate heat exchanger 100.After flowing in pumping chamber (plenum volume) 105, as shown in multiple arrows 107, cooling medium continues to flow through major loop pipeline 90.Can understand, due to the heat conduction occurring in intermediate heat exchanger 100, the cooling medium that leaves pumping chamber 105 is cooling.The first pump 110 is coupled with major loop pipeline 90, and the reactor coolant fluid transmitting 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 of 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 secondary hot branch road pipeline section 130, to form the closed-loop path of defining subloop pipeline 120.It can be suitably the fluid of Liquid Sodium or Liquid Sodium potpourri that the subloop pipeline 120 being defined by the hot branch road pipeline section 130 of pair and secondary cold branch road pipeline section 140 comprises.Owing to just describing, secondary hot branch road pipeline section 130 extends to steam generator and superheater assembly 143 (hereinafter referred to as " steam generator 143 ") from intermediate heat exchanger 100.By after steam generator 143, due to the heat conduction occurring in steam generator 143, the cooling medium that flows through subloop pipeline 120 and leaving water steam generator 143 is in than entering in the temperature that steam generator 143 is before low.By after steam generator 143, along " cold " branch road pipeline section 140 terminating on intermediate heat exchanger 100, as pumping cooling medium by the second pump 145.Below will immediately steam generator 143 usually be described and generate the mode of water vapour.

Also referring again to Fig. 1, being in steam generator 143 is the water body 150 remaining on predetermined temperature and pressure.The fluid that flows through secondary hot branch road pipeline section 130 is given its heat in the water body 150 being in than in the low temperature of the fluid that flows through secondary hot branch road pipeline section 130.Along with its heat is given water body 150 by the fluid that flows through secondary hot branch road pipeline section 130, the temperature according in steam generator 143 and pressure are flashed to water vapour 160 by a part of water body 150.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 connections.Revolving wormgear machine 180 is coupled with steam pipe 170, so that turbine 180 is along with water vapour 160 is therefrom by rotating.Generate electricity along with turbine 180 rotates as the generator 190 being connected with turbine 180 by revolving wormgear arbor 195.In addition, condenser 200 is coupled with steam pipe 170, receives by the water vapour of turbine 180.Condenser 200 makes water recovery become aqueous water, and any used heat is passed to as cooling tower 210, the heating radiator being associated with reactor 10.By being inserted in the 3rd pump 220 between condenser 200 and steam generator 143, the aqueous water that condenser 200 is condensed is pumped into steam generator 143 along steam pipe 170 from condenser 200.

Forward now Fig. 2 to, 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 to reactor core 20 and define the hexagonal configuration configuration that is referred to as 230.Alternately, nuclear fission module 30 can be arranged as to reactor core 20 and define the cylindrical shape configuration that is referred to as 240.Substitute as another kind, nuclear fission module 30 can be arranged as to reactor core 20 and define the parallelepiped-shaped configuration that is 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, with the configuration-independent of selecting for reactor core 20, by many separate, extending longitudinally and can vertically move control rod 260 and be arranged in symmetrically along the length of predetermined quantity nuclear fission module 30 in the control rod guide tube extending or involucrum (not shown).Be shown as the control rod 260 being arranged in predetermined quantity hexagonal configuration nuclear fission module 30 and control the neutron fission reaction occurring in nuclear fission module 30.Control rod 260 comprises and has the suitable neutron absorber material that can accept large neutron-absorption cross-section.About this respect, absorbing material can be from substantially by the metal of selecting the group forming as follows or metalloid: lithium, silver, indium, cadmium, boron, cobalt, hafnium, dysprosium, gadolinium, samarium, erbium, europium and composition thereof.Alternately, absorbing material can be from substantially by the compound of selecting the group forming 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 control the neutron flux curve that strides across reactor core 20, and therefore impact strides across the temperature curve of reactor core 20.

With reference to Fig. 5 A and 5B, they show the alternate embodiments of nuclear fission module 30.Can understand, nuclear fission module 30 is without neutron activation.In other words, nuclear fission module 30 is without 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 the reproducing kernel fission module that comprises core regrown material or the module of fissioning the reflective core that comprises reflecting material.Alternately, in one embodiment, nuclear fission module 30 can comprise fuel rod 40 with core regeneration rod or the combination of reflection rod.For example, in Fig. 5 A, many can be arranged in nuclear fission module 30 with fuel rod 40 combinations by fertile nuclei regeneration rod 270.Also can there is control rod 260.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 assembly.In Fig. 5 B, many neutron relfector rods 274 and fuel rod 40 combinations are arranged in nuclear fission module 30.Also can there is control rod 260.Reflecting material can be from substantially by the material of selecting the group forming 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 understand, 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 Fig. 5 C, and comprise the regeneration blanket with multiple reproducing kernels fission modules 276 that can fertile material around surrounding's disposed inboard of parallelepiped-shaped reactor core 250.The regeneration blanket fissile material of regenerating therein.

Turn back to Fig. 4, with the configuration-independent of selecting 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, by comprise without limitation as U-233, U-235 or Pu-239 can fissionable material the relatively little and dismountable nuclear fission igniter 280 of moderate enriched isotope be suitably placed in reactor core 250.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 that chain reaction becomes is self-holding, just can remove lighter 280.

Referring again to Fig. 4, lighter 280 causes three-dimensional, detonation row ripple or " combustion wave " 290 with width " x ".In the time that lighter 280 its neutrons of release cause " igniting ", combustion wave 290 is outwards advanced near the lighters 280 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 and receive at least a portion burning row ripple 290 along with combustion wave 290.The speed of burning row ripple 290 can be constant or non-constant.Therefore the speed of, can control combustion ripple 290 propagating.For example,, to be scheduled to or programming mode vertically moves aforementioned control rod 260 (referring to Fig. 5) and can drive or reduce the neutron reaction of the fuel rod 40 being arranged in nuclear fission module 30 downwards.Like this, with respect to comparing downward driving in the neutron reaction of combustion wave 290 " unburned " fuel rod 40 above or having reduced the neutron reaction of the current fuel rod burning 40 on the position of combustion wave 290.This result has provided the combustion wave direction of propagation of arrow 295 indications.

At on November 28th, 2006 submission of the name taking people such as RoderickA.Hyde and denomination of invention pending trial U.S. Patent application the 11/605th in " Automated Nuclear Power Reactor For Long-Term Operation (the automatic power producer of long-time running) ", the ultimate principle of such row ripple fission-type reactor is disclosed in No. 943 in more detail, this application has transferred the application's assignee, by reference its whole open text is incorporated herein at this.

With reference to Fig. 6 and 7, they show upright adjacent hexagonal configuration nuclear fission module 30.Although only show three adjacent nuclear fission modules 30, should be understood that and have a large amount of nuclear fission modules 30 in reactor core 20.In addition, each nuclear fission module 30 comprises many aforementioned 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 therefrom passing through.Relative opening 370 has the openend 380 that allows 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 that covers each nuclear fission module 30.Reactor core upper backup pad 400 also defines the multiple chutes 410 that allow cooling medium therefrom to flow through.

As previously mentioned, with the configuration-independent that reactor core 20 is selected, importantly control the temperature of reactor core 20 and nuclear fission module 30 wherein.Due to several respects reason, suitable temperature control is very important.For example, if peak temperature exceedes material limits, may cause fire damage to reactor core structure material.Such peak temperature may be because having changed the engineering properties of structure, those especially relevant with thermal creep character but not shortened as desired the operation life of the structure that stands such peak temperature.In addition, reactor capability density is subject to core structural material to bear the capabilities limits of such high temperature injury-freely.In addition, reactor 10 can be alternatively for the test as determining the test of the impact of temperature on pile materials.Controlling reactor core temperature is important for successfully carrying out such test.In addition, in the case of lacking around reactor core 20 neutron relfector or neutron reproduction blanket around, reside in reactor core 20 in the heart or near nuclear fission module 30 can generate than residing in that reactor core 20 is gone up around or near the heat of nuclear fission module more than 30.Therefore, because near reactor core 20 center compared with thermonuclear fission module 30 by near the high coolant mass flow rate of nuclear fission module 30 around involving than reactor core 20, so stride across reactor core 20, even coolant mass flow rate is provided is inadequate.Herein the technology of processing these concerns that provides disclosed.

Along coolant flow paths or the fluid stream of flow arrow 420 indications, reactor coolant is flowed to nuclear fission module 30 with reference to figure 1,6 and 7, the first pumps 110 and major loop 90.Then, reactor coolant continues to flow along coolant flow paths 420, flows through the openend 380 forming in lower supporting plate 360.As described in more detail below, reactor coolant can be for taking away the selected several of heat or the cooling locational nuclear fission module 30 that is in burning row ripple 290 from the locational nuclear fission module 30 that is in burning row ripple 290 selected several.As described in more detail below, nuclear fission module 30 can be at least partly according to combustion wave 290 whether be in nuclear fission module 30 or near, whether in nuclear fission module 30 or near detect or otherwise whether reside in nuclear fission module 30 or near selection.

Referring again to Fig. 1,6 and 7, in order to reach the desired result of selected of cooling nuclear fission module 30, regulate subassembly 430 and nuclear fission module 30 to be coupled adjustable flow.Flow regulation subassembly 430 responds the flow of combustion wave 290 (referring to Fig. 4) with respect to the position of nuclear fission module 30 and response some the operational factor control cooling medium relevant with nuclear fission module 30.In other words, flow regulation subassembly 430 can or be configured to when there is combustion wave 290 (, the combustion wave 290 that intensity is less) in a small amount in nuclear fission module 30 time, and the cooling medium of small number is relatively 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 (, the combustion wave 290 that intensity is larger) in nuclear fission module 30 time, 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 extend by relative opening, to regulate the flow of the fluid stream that enters 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 has been equipped with controlled flow resistance.Flow regulation subassembly 430 comprises and has the substantial cylindrical first of many first pore zones 460 or outer tube 450, the first pore zones 460 and define several separately around outer tube 450 radially-arranged multiple axially-spaceds the first hole or the first controllable flow gap 470.Due to reason provided below, outer tube 450 further comprises first joint 480 can with hexagonal configuration xsect.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 below open more in detail, flow regulation subassembly 430 further comprises substantial cylindrical second or the inner sleeve 530 that can be received into spirally in outer tube 450.In one embodiment, during manufacturing nuclear fission module 30, can make inner sleeve 530 and nuclear fission module 30 form entirety, so that inner sleeve 530 is permanent parts of 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 part of nuclear fission module 30.In any embodiment, inner sleeve 530 all comprises many second pore zone 540, the second pore zones 540 and defines several separately around inner sleeve 530 radially-arranged multiple axially-spaceds the second hole or the second controllable flow gap 550.Inner sleeve 530 further comprises size and makes external belt screw thread the second joint 560 in the threaded inner portion cavity 500 that can be received into spirally the bottom 490 that belongs to outer tube 450.The top 570 of inner sleeve 530 comprises a cap 580, and as previously mentioned, cylinder cap 580 can for good and all also can for good and all not form entirety with nuclear fission module 30.Endoporus 590 extends by top 570, comprises by cylinder cap 580, to allow cooling medium therefrom pass through.What be coupled with cylinder cap 580 and fuel rod 580 can be the conical butt funnel part 600 with inside surface 605, the internal communication of conical butt funnel part 600 and endoporus 590 and cylindrical shell 43, to make cooling medium pass through to resident cylindrical shell 43 ground of fuel rod 40 from endoporus 590.As previously mentioned, nuclear fission module 30 can cause or be configured to cause temperature correlation reactions change.Therefore, the coolant flow that flow control regulates subassembly 430 to be configured at least partly by controlling to nuclear fission module 30 is controlled 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 comprise be referred to as 606 anti-ly turn configuration, to prevent that outer tube 450 from rotating with respect to inner sleeve 530.About this respect, outer tube 450 defines the multiple grooves as groove 607a and 607b, forms multiple teat 608a of entirety and separately of 608b so that pairing ground is received 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, prevented that inner sleeve 530 from rotating with respect to outer tube 450.

From Fig. 8 E, can the best see, the first joint 480 can rotate with respect to outer tube 450.About this respect, the first joint 480 comprises the annular flange 608c being slidably received within the ring groove 608d forming in outer tube 450.Like this, the first joint 480 can be free to slide and rotate with respect to outer tube 450.The first joint 480 can rotate along any direction of curved arrow 608e or 608f indication with being free to slide.In addition, along with the first joint 480 is as the direction along arrow 608e, the rotation slidably automatically 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, the 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, the first sleeve pipes 450 by the direction at vertical arrows 408h indication along along upwards translation or the rising of its longitudinal axis.Owing to there being anti-upwards translation or the rising of configuration 450 directions at arrow 608h of 608, the first sleeve pipe that turn.Along with upwards translation or rising scheduled volume of the first sleeve pipe 450, the first hole 470 will be closed by the second pore zone 540 of inner sleeve 530 gradually, covers, and blocks, and otherwise stops up.In addition, can understand, along with upwards translation or rising scheduled volume of the first sleeve pipe 450, the second hole 550 will be closed by the first pore zone 460 of outer tube 450 gradually, covers, and blocks, and otherwise stops up.Close gradually by this way, cover, block, and otherwise obstruction the first hole 470 and the second hole 550 reduce cooling medium changeably by the flow in the first hole 470 and the second hole 550.Can understand, first interface 480 is as the direction along curved arrow 608f, rotation in the opposite direction make the first hole 470 and the second hole 550 open gradually, open, disclose and otherwise dredging, to increase changeably cooling medium by the flow in the first hole 470 and the second hole 550.

Therefore, with reference to Fig. 7,8,8A, 8B, 8C, 8D, 8E, 9 and 10, as described in current, by using two kinds of different parts-outer tubes 450 and inner sleeve 530, realize at least partly the flow control in nuclear fission module 30.As previously mentioned, in the time manufacturing nuclear fission module 30 for the first time, can make inner sleeve 530 and nuclear fission module 30 form entirety.But if necessary, inner sleeve can separate formation with nuclear fission module 30, but is attached thereto, instead of in the time manufacturing nuclear fission module 30 for the first time, 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 slides in the outside of inner sleeve 530, has corresponding multiple the first hole 470.Outer tube 450 and inner sleeve 530 are concentric, and hole 470/550 always aims at, so that along radially or turning axle coupling.The flow of cooling medium is controlled at the relative position of axial 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, one engage and limited the rotation of outer tube 450 with respect to inner sleeve 530 separately of teat 608a and 608b and groove 607a and 607b.This feature slides axially outer tube 450 on inner sleeve 530, but there is no relative rotation between outer tube 450 and inner sleeve 530.The fine tuning of coolant flow is to realize with respect to sliding axially gradually of inner sleeve 530 by outer tube 450.Therefore, the first joint 480 is opened 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, thereby realize the fine tuning in hole 470/550, therefore realize the fine tuning of coolant flow.

From Figure 11, can the best see, can exist as flow regulation subassembly 609a and 609b, be assigned to the multiple of single core fission module 30 and regulate subassembly compared with low discharge.Regulate subassembly 609a and 609b to be assigned to single core fission module 30 compared with low discharge to provide the alternative configuration that coolant flow is offered to nuclear fission module 30 by multiple.In addition, by multiple compared with low discharge regulate subassembly 609a and 609b to be assigned to separately single core fission module 30 provides abundant control separately or the different piece of single core fission module 30 in the possibility of Temperature Distribution.Having this may be because can control respectively the fluid flow that regulates subassembly 609a and 609b compared with low discharge by each.

With reference to Figure 12,13,14,15, and 16, they show adjusts or regulates the flow regulation subassembly 430 under the running status of the cooling fluid flow that enters nuclear fission module 30.As below more fully open, flow regulation subassembly 430 defines the flow control assembly that is 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 and, 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 changeably the coolant flow that enters nuclear fission module 30.In addition, if necessary, balladeur train subassembly 610 can be sent to nuclear fission module 30 by outer tube 450.

With reference to Figure 13,14,15, and 16, the configuration of balladeur train subassembly 610 is described now.Balladeur train subassembly 610 comprises the long bridge 620 of crossing over reactor core 20, so that by above multiple can vertical sliding moving sleeve spanner 630 being supported on.Due to disclosed reason below, 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 respectively first to move bridge device 640a and second and move bridge device 640b.Moving the toothed gearing (also not shown) that bridge device 640a and 640b can drive by motor (not shown) operates.Such motor can be positioned at the outside of reactor core 20, the corrosive attack and the heat that cause by reactor core 20 with the circulate coolant of avoiding as Liquid Sodium.Eachly move bridge device 640a and 640b at least comprises respectively a wheel 650a and 650b, to make to move bridge device 640a and a 640b transversely movement separately of spaced-apart parallel track 660a and 660b simultaneously.Move bridge device 640a and 640b and can or be configured to any direction at arrow 663 indications along track 660a and 660b travelling bridge 620.That be connected with each track 660a and 660b can be respectively rail supported body 665a and 665b, so that above track 660a and 660b are supported on.

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 and departs from the first joint 480 of outer tube 450.In an embodiment of balladeur train subassembly 610, several row tubular keys 630 are configured to be referred to as 670 lead screw device and drive.Lead screw device 670 has the lead screw 680 of external thread 690 of rotating shaft 700 that is configured to engage spirally around belonging to each tubular key 630.Lead screw 680 can be driven by the mechanical drive system 705 that comprises the mechanical linkage 707 being coupled with lead screw 680.In the time that mechanical linkage 707 drives lead screw 680, due to lead screw 680 and the screw-threaded engagement of the external thread 690 around rotating shaft 700, lead screw 680 will rotate or rotating shaft 700.As shown in the figure, in the time that the hexagonal configuration recess 700a on rotating shaft 700 tops engages with hexagonal configuration the first joint 480, 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, the mode of every rotating shaft 700 is risen and reduces in description now selectively.About this respect, band external thread long mechanical linkage extension 708 engages with the first gear 709, so that along any direction rotation first gear 709 of curved arrow 709a and 709b.For example, along with mechanical linkage extension 708 is along the translation of one of the direction 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 the first bar 709d also rotates equal number, because the external thread of the first bar 709d can engage spirally with by the internal thread (not shown) being formed centrally in the first gear 709.The second gear 709e has the internal thread (not shown) by being wherein formed centrally, to 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 be along the first bar 709d translation.The second gear 709e moves to the position of a predetermined rotating shaft 700 always along the first bar 709d.Can understand, the second external thread of gear 709e or the spacing of the gear teeth are to form like this, and that is exactly not to producing and disturb around the externally threaded spacing of rotating shaft 700, so that the second gear 709e can carry out without hindrance along the translation of the first bar 709e.Described in current, be also equipped with the 3rd gear 709f.About this respect, the 3rd gear 709f be arranged in the either side of bosom the first bar 709d and the length second bar 709g adjacent with bosom the first bar 709d and long the 3rd bar 709h coupling.The 3rd gear 709f is driven by aforementioned mechanical linkage extension 708, and it can move to the second place engaging with the 3rd gear 709f from the primary importance being coupled with the first gear 709.Along with the 3rd gear 709f rotation, the second bar 709g and the 3rd bar 709h are by the longitudinal axis rotation around the first bar 709d, to make the longitudinal axis rotation of the second gear 709e around the first bar 709d.Along with the second gear 709e rotation, 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, make tubular key translation up or down.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 can be by rotation and an axial translation respectively separately of many sealings that are coupled with rotating shaft 700, reversible the first motor 710.The first motor 710 seals, can air cooling, and can be corrosive attack and the heat effects of the cooling medium of Liquid Sodium or Liquid Sodium potpourri to protect the first motor 710 to avoid.The first motor 710 is configured to vertical mobile shaft 700 selectively.Motor 710 can be along first direction or the second direction running contrary with first direction from the rotor of motor 710, is reversible to move up or down respectively in the meaning of rotating shaft 700.The running of mechanical drive system 705 or motor 710 can suitably be controlled by the controller or the control module 720 that are coupled with it.Every 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) that is 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) that is located at Chicago, Illinois, USA city.According to another embodiment, tubular key 630 can move respectively by transmitting set-acceptor device, and this transmitting set-acceptor device comprises many sealings, air cooling, reversible second motor 730 that can turn round respectively by receiving the radiofrequency signal that launch of transmitting set 740.The second motor 730 seals, can air cooling, and to protect the second motor 730 to avoid corrosive attack and the heat effects of sodium cooling agent.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 be from being located at (the Myostat Motion Control of Myostat Electric Machine Control company of Ontario, Canada, Incorporated, Ontario, Canada) the customization motor and the transmitter that buy.According to another embodiment, tubular key 630 can move respectively by being referred to as fiber optic emitter-acceptor device of 742, and this fiber optic emitter-acceptor device 742 has multifiber cable 745, so that by light transmission running reversible electric machine device.

From Figure 14, can the best see, flow control assembly 615, therefore flow regulation subassembly 433 can according to or the operation of the response operational factor relevant with nuclear fission module 30.About this respect, at least one sensor 750 can be arranged in nuclear fission module 30, with the state of sensing operational factor.The operational factor of sensor 750 sensings can be the Current Temperatures in nuclear fission module 30.Alternately, the operational factor of sensor 750 sensings can be the former temperature in nuclear fission module 30.For sensing temperature, sensor 750 can be can be from being located at (the Thermocoax of Thermocoax company of State of Georgia, US Alpha Li Ta, Incorporated, Alpharetta, Georgia U.S.A.) the thermopair equipment or the temperature sensor that buy.Substitute as another kind, the operational factor of sensor 750 sensings can be the neutron flux in nuclear fission module 30.For sensing 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 of sensor 750 sensings can be the feature isotope in nuclear fission module 30.Feature isotope can be fission product, activating isotope, the transformation isotope forming by regeneration or further feature isotope.Another example is that the operational factor of sensor 750 sensings can be the neutron fluence in nuclear fission module 30.As technical well-known, neutron fluence is defined by the neutron flux in certain period upper integral, the unit area neutron number that representative is passed through at that time durations.As another example, the operational factor of sensor 750 sensings can be fission module pressure, at normal operation period, for exemplary sodium cooling reactor approximately 10 bar (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 approximately 138 bar (, about 2000psi).Alternately, the fission module pressure of sensor 750 sensings can be static fluid pressure or fission product pressure.For sensing is dynamic or fission module pressure, sensor 750 can be can be from being located at (the Kaman Measuring Systems of Kaman's measuring system company of 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 meters ", can be from being located at (the Instrumart of instrument company of Vermont ,Usa Williston, Incorporated, Williston, Vermont U.S.A.) the suitable flowmeter that buys.In addition, the operational factor of sensor 750 sensings can be by suitably determining based on computerized algorithm.Can realize diversified algorithm, 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 such algorithms of algorithm known of the signal of instruction pressure or temperature.According to another example, operational factor can be the action that operating personnel start to take.That is to say, any suitable operational factor that flow regulation subassembly 430 can operation response personnel be determined is adjusted.And flow regulation subassembly 430 can respond by the definite operational factor of suitable FEEDBACK CONTROL and adjust.In addition, flow regulation subassembly 430 can respond the definite operational factor of automatic control system and adjusts.In addition the variation that, flow regulation subassembly 430 can respond decay heat is adjusted.About this respect, decay heat has reduced at " afterbody " of combustion wave 290 (referring to Fig. 4).The existence that detects the afterbody of combustion wave 290 can be for reducing in time coolant flow speed, to take reducing of this decay heat found at the afterbody of combustion wave 290 into account.When nuclear fission module 30 resides in combustion wave 290 below time, situation is especially true.In this case, the decay heat that flow regulation subassembly 430 is taken nuclear fission module 30 into account is along with nuclear fission module 30 changes with respect to the change of distance of combustion wave 290.The state of the such operational factor of sensing can contribute to suitably to control and adjust the operation of flow control assembly 615, therefore suitably controls and adjust the temperature in 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 as controller 720 and 740 and flow regulation subassembly 430 in conjunction with suitably controlling fluid flow.That is to say, the predetermined input of controller 720 and 740 is signals that sensor as aforementioned 750 produces.For example, 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 pass through the processing of reactor control system (not shown).For example, the signal that reactor control system produces like this can be from gauge or detector, and process through the computing machine in reactor pulpit or operating personnel, 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 the instruction according to herein, the flow of cooling medium is controlled and regulated to the time that flow control assembly 615 can arrive and/or leave nuclear fission module 30 according to burning row ripple 290.In addition, flow control assembly 615 can approach according to burning row ripple 290 flow of nuclear fission module 30 or near the control of time nuclear fission module 30 and adjusting cooling medium.The flow of cooling medium can also control and regulate according to the aforementioned width " x " of combustion wave 290 to flow control assembly 615.Along with combustion wave 290 is advanced by nuclear fission module 30, the arrival of combustion wave 290 and leave by the aforementioned operational factor of sensing any one detect.For example, flow control assembly 615 can be according to the flow of the rate of heat production control of sensing in nuclear fission module 30 and adjusting cooling medium.It should be obvious that for the person of ordinary skill of the art, in some cases, only input signal just can be controlled 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 for example, according to the expectation value of the operational factor in nuclear fission module 30 (, temperature) alternatives with the actual value of the operational factor of sensing in nuclear fission module 30.As current more detailed description, adjust to the fluid flow of nuclear fission module 30 so as to make the actual value of operational factor and the expectation value of operational factor basically identical.In order to realize this result, by activate and move bridge device 640a and 640b makes the bridge 620 that belongs to balladeur train subassembly 630 advance along track 660a and 660b simultaneously.Along with bridge 620 is advanced along track 660a and 660b, bridge 620 will be advanced below reactor core lower supporting plate 360.More fully describe as current, bridge 620 finally stops on reactor core lower supporting plate 360 precalculated position below according to the advancing of it that relatively make of the expectation value of the actual value of operational factor of sensor 750 sensings in nuclear fission module 30 and the operational factor of nuclear fission module 30.Moving the startup of advancing and the scope of bridge device 640a and 640b can, as by controller 720 or 740, control by suitable controller.About this respect, controller 720 or 740 will stop advancing of bridge 620 according to the position of selected of multiple nuclear fission modules 30.As described above, the nuclear fission module 30 that adjust can be according to basically identical selection whether between the expectation value of the operational factor of the actual value of the operational factor at sensor 750 sensings and nuclear fission module 30.Then, make selected one of multiple hexagonal socket wrenches 630 to move vertically upward to match and engage with sexangle the first joint 480.After tubular key 630 engages with the first joint 480, rotating shaft 700 is rotated, to tubular key 630 is rotated.Making rotating shaft 700 rotations is by realizing with aforementioned lead screw device 670, the first motor 710 or second motor 730 of controller 720 or 740 couplings.

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 slidings, the first pore zone 460 of outer tube 450 will cut out gradually, cover, block, or otherwise stop up the second hole 550 of inner sleeve 530, and the second pore zone 540 of inner sleeve 530 cuts out while gradually, covering, block, or otherwise the first hole 470 of obstruction outer tube 450.Close gradually, cover, block, or otherwise obstruction the first hole 470 and the second hole 550 reduce changeably by the flow of the cooling medium in the first hole 470 and the second hole 550.In this case, in order to allow cooling medium flow through completely, the second hole 550 and the first hole 470 may be aimed in the past.Alternately, in order to allow cooling medium part flow through, the second hole 550 and the first hole 470 may be in the past that part is aimed at.

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 down slidings, the 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 simultaneously be opened gradually, 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 have increased changeably by the flow of the cooling medium in the first hole 470 and the second hole 550.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, for part limits or partly 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, comprise flow regulation subassembly 430 and balladeur train subassembly 610 flow control assembly 615 use one by one module (, one by one fuel assembly ground) realized variable coolant stream.This makes to stride across reactor core 20 ground according to the position of combustion wave 290 in reactor core 20 or non-homogeneous Temperature Distribution and changes coolant flow.

exemplary methods

The exemplary methods that description is now associated with the example embodiment of fission-type reactor and flow control assembly.

With reference to Figure 20 A-20S, they provide the exemplary methods of moving fission-type reactor.

Forward now Figure 20 A to, a kind of exemplary methods 760 of operation fission-type reactor is from square 770.In square 780, the method is included in and on the position with respect to nuclear fission module, produces at least a portion burning row ripple.In square 790, response is with respect to the position of nuclear fission module, and operation flow control assembly is to regulate the flow of fluid.In square 800, finish the method.

In Figure 20 B, a kind of exemplary methods 810 of operation fission-type reactor is from square 820.In square 830, on the position with respect to nuclear fission module, produce at least a portion burning row ripple.In square 840, response is with respect to the position of nuclear fission module, and the flow control assembly of operation and the coupling of nuclear fission module is to regulate the flow of fluid.In square 850, operation flow regulation subassembly.In square 860, finish the method.

In Figure 20 C, the another kind of exemplary methods 870 of operation fission-type reactor is from square 880.In square 890, on the position with respect to nuclear fission module, produce at least a portion burning row ripple.In square 900, response is with respect to the position of nuclear fission module, and the flow control assembly of operation and the coupling of nuclear fission module is to regulate the flow of fluid.In square 910, operate flow regulation subassembly.In square 920, according to the operational factor operation flow regulation subassembly being associated with nuclear fission module.In square 930, finish the method.

In Figure 20 D, the further exemplary methods 940 of operation fission-type reactor is from square 950.In square 960, on the position with respect to nuclear fission module, produce at least a portion burning row ripple.In square 970, response is with respect to the position of nuclear fission module, and the flow control assembly of operation and the coupling of nuclear fission module is to regulate the flow of fluid.In square 980, operate flow regulation subassembly.In square 990, the operational factor that response is associated with nuclear fission module is adjusted flow regulation subassembly.In square 1000, finish the method.

In Figure 20 E, the another kind of exemplary methods 1010 of operation fission-type reactor is from square 1020.In square 1030, on the position with respect to nuclear fission module, produce at least a portion burning row ripple.In square 1040, response is with respect to the position of nuclear fission module, and the flow control assembly of operation and the coupling of nuclear fission module is to regulate the flow of fluid.In square 1050, operate flow regulation subassembly.In square 1060, reconfigure flow regulation subassembly according to the predetermined input of flow regulation subassembly.In square 1070, finish the method.

In Figure 20 F, another exemplary methods 1080 of operation fission-type reactor is from square 1090.In square 1100, on the position with respect to nuclear fission module, produce at least a portion burning row ripple.In square 1110, response is with respect to the position of nuclear fission module, and the flow control assembly of operation and the coupling of nuclear fission module is to regulate the flow of fluid.In square 1120, operate flow regulation subassembly.In square 1130, realize controlled flow resistance.In square 1140, finish the method.

In Figure 20 G, a kind of exemplary methods 1150 of operation fission-type reactor is from square 1160.In square 1170, on the position with respect to nuclear fission module, produce at least a portion burning row ripple.In square 1180, response is with respect to the position of nuclear fission module, and the flow control assembly of operation and the coupling of nuclear fission module is to regulate the flow of fluid.In square 1190, operate flow regulation subassembly.In square 1200, the second sleeve pipe is inserted in the first sleeve pipe, first set pipe has the first hole, and the second sleeve pipe has the second hole that can aim at the first hole.In square 1210, finish the method.

In Figure 20 H, the another kind of exemplary methods 1220 of operation fission-type reactor is from square 1230.In square 1240, on the position with respect to nuclear fission module, produce at least a portion burning row ripple.In square 1250, response is with respect to the position of nuclear fission module, and the flow control assembly of operation and the coupling of nuclear fission module is to regulate the flow of fluid.In square 1260, operate flow regulation subassembly.In square 1270, the balladeur train subassembly of operation and the coupling of flow regulation subassembly.In square 1280, finish the method.

In Figure 20 I, the other exemplary methods 1290 of operation fission-type reactor is from square 1300.In square 1310, on the position with respect to nuclear fission module, produce at least a portion burning row ripple.In square 1320, response is with respect to the position of nuclear fission module, and the flow control assembly of operation and the coupling of nuclear fission module is to regulate the flow of fluid.In square 1330, operate flow regulation subassembly.In square 1340, by temperature sensor and nuclear fission module and the coupling of flow regulation subassembly.In square 1350, finish the method.

In Figure 20 J, the further exemplary methods 1360 of operation fission-type reactor is from square 1370.In square 1380, on the position with respect to nuclear fission module, produce at least a portion burning row ripple.In square 1390, response is with respect to the position of nuclear fission module, and the flow control assembly of operation and the coupling of nuclear fission module is to regulate the flow of fluid.In square 1400, by the time operation flow control assembly with respect to the position of the position of nuclear fission module according to combustion wave arrival, response is with respect to the flow of the position control fluid of the position of nuclear fission module.In square 1410, finish the method.

In Figure 20 K, another exemplary methods 1420 of operation fission-type reactor is from square 1430.In square 1440, on the position with respect to nuclear fission module, produce at least a portion burning row ripple.In square 1450, response is with respect to the position of nuclear fission module, and the flow control assembly of operation and the coupling of nuclear fission module is to regulate the flow of fluid.In square 1460, by leave the time operation flow control assembly with respect to the position of nuclear fission module according to combustion wave, response is with respect to the flow of the position control fluid of nuclear fission module.In square 1470, finish the method.

In Figure 20 L, the another kind of exemplary methods 1480 of operation fission-type reactor is from square 1490.In square 1500, on the position with respect to nuclear fission module, produce at least a portion burning row ripple.In square 1510, response is with respect to the position of nuclear fission module, and the flow control assembly of operation and the coupling of nuclear fission module is to regulate the flow of fluid.In square 1520, by approaching the time operation flow control assembly with respect to the position of nuclear fission module according to combustion wave, response is with respect to the flow of the position control fluid of nuclear fission module.In square 1530, finish the method.

In Figure 20 M, a kind of exemplary methods 1540 of operation fission-type reactor is from square 1550.In square 1560, on the position with respect to nuclear fission module, produce at least a portion burning row ripple.In square 1570, response is with respect to the position of nuclear fission module, and the flow control assembly of operation and the coupling of nuclear fission module is to regulate the flow of fluid.In square 1580, according to the flow of the width control fluid of combustion wave.In square 1590, finish the method.

In Figure 20 N, a kind of exemplary methods 1600 of operation fission-type reactor is from square 1610.In square 1620, on the position with respect to nuclear fission module, produce at least a portion burning row ripple.In square 1630, response is with respect to the position of nuclear fission module, and the flow control assembly of operation and the coupling of nuclear fission module is to regulate the flow of fluid.In square 1640, by the flow of the rate of heat production operation flow control assembly control fluid according in nuclear fission module.In square 1650, finish the method.

In Figure 20 O, a kind of exemplary methods 1660 of operation fission-type reactor is from square 1670.In square 1680, on the position with respect to nuclear fission module, produce at least a portion burning row ripple.In square 1690, response is with respect to the position of nuclear fission module, and the flow control assembly of operation and the coupling of nuclear fission module is to regulate the flow of fluid.In square 1700, by the flow of the temperature operation flow control assembly control fluid according in nuclear fission module.In square 1710, finish the method.

In Figure 20 P, a kind of exemplary methods 1720 of operation fission-type reactor is from square 1730.In square 1740, on the position with respect to nuclear fission module, produce at least a portion burning row ripple.In square 1750, response is with respect to the position of nuclear fission module, and the flow control assembly of operation and the coupling of nuclear fission module is to regulate the flow of fluid.In square 1760, by the flow of the neutron flux operation flow control assembly control fluid according in nuclear fission module.In square 1770, finish the method.

In Figure 20 Q, a kind of exemplary methods 1780 of operation fission-type reactor is from square 1790.In square 1800, on the position with respect to nuclear fission module, produce at least a portion burning row ripple.In square 1810, response is with respect to the position of nuclear fission module, and the flow control assembly of operation and the coupling of nuclear fission module is to regulate the flow of fluid.In square 1820, on the position with respect to nuclear fission fuel assembly, produce at least a portion burning row ripple.In square 1830, finish the method.

In Figure 20 R, a kind of exemplary methods 1840 of operation fission-type reactor is from square 1850.In square 1860, on the position with respect to nuclear fission module, produce at least a portion burning row ripple.In square 1870, response is with respect to the position of nuclear fission module, and the flow control assembly of operation and the coupling of nuclear fission module is to regulate the flow of fluid.In square 1880, with respect to can fertile nuclei producing at least a portion burning row ripple on the position of regeneration assembly.In square 1890, finish the method.

In Figure 20 S, a kind of exemplary methods 1900 of operation fission-type reactor is from square 1910.In square 1920, on the position with respect to nuclear fission module, produce at least a portion burning row ripple.In square 1930, response is with respect to the position of nuclear fission module, and the flow control assembly of operation and the coupling of nuclear fission module is to regulate the flow of fluid.In square 1940, on the position with respect to neutron relfector assembly, produce at least a portion burning row ripple.In square 1950, finish the method.

With reference to Figure 21 A-21H, they provide assembling to be used in the exemplary methods of the flow control assembly in fission-type reactor.

Forward now Figure 21 A to, a kind of exemplary methods 1960 that assembling is used in the flow control assembly in fission-type reactor is from square 1970.In square 1980, receive flow regulation subassembly.In square 1990, finish the method.

In Figure 21 B, the another kind of exemplary methods 2000 that assembling is used in the flow control assembly in fission-type reactor is from square 2010.In square 2020, receive balladeur train subassembly.In square 2030, finish the method.

In Figure 21 C, the another kind of exemplary methods 2040 that assembling is used in the flow control assembly in fission-type reactor is from square 2050.In square 2060, receive flow regulation subassembly.In square 2070, receive first sleeve pipe with the first hole.In square 2080, the second sleeve pipe is inserted in the first sleeve pipe, the second sleeve pipe has the second hole that can aim at the first hole, and the first sleeve pipe be configured to rotatable, to the first hole is rotated into the second hole and is aimed at.In square 2090, by balladeur train subassembly and the coupling of flow regulation subassembly.In square 2100, finish the method.

In Figure 21 D, another exemplary methods 2110 that assembling is used in the flow control assembly in fission-type reactor is from square 2120.In square 2130, receive flow regulation subassembly.In square 2140, receive first sleeve pipe with the first hole.In square 2150, the second sleeve pipe is inserted in the first sleeve pipe, the second sleeve pipe has the second hole that can aim at the first hole.In square 2160, by balladeur train subassembly and the coupling of flow regulation subassembly.In square 2170, by balladeur train subassembly and the coupling of flow regulation subassembly, so that flow regulation subassembly is sent to fuel assembly by balladeur train subassembly.In square 2180, finish the method.

In Figure 21 E, the further exemplary methods 2190 that assembling is used in the flow control assembly in fission-type reactor is from square 2200.In square 2210, receive flow regulation subassembly.In square 2220, receive first sleeve pipe with the first hole.In square 2230, the second sleeve pipe is inserted in the first sleeve pipe, the second sleeve pipe has the second hole that can aim at the first hole.In square 2240, by balladeur train subassembly and the coupling of flow regulation subassembly.In square 2250, by balladeur train subassembly and the coupling of flow regulation subassembly, to drive balladeur train subassembly by lead screw device.In square 2260, finish the method.

In Figure 21 F, a kind of exemplary methods 2270 that assembling is used in the flow control assembly in fission-type reactor is from square 2280.In square 2290, receive flow regulation subassembly.In square 2300, receive first sleeve pipe with the first hole.In square 2310, the second sleeve pipe is inserted in the first sleeve pipe, the second sleeve pipe has the second hole that can aim at the first hole, and the first sleeve pipe be configured to rotatable, to the first hole is rotated into the second hole and is aimed at.In square 2320, by balladeur train subassembly and the coupling of flow regulation subassembly.In square 2330, coupling balladeur train subassembly, to drive balladeur train subassembly by reversible electric machine device.In square 2340, finish the method.

In Figure 21 G, a kind of exemplary methods 2350 that assembling is used in the flow control assembly in fission-type reactor is from square 2360.In square 2370, receive flow regulation subassembly.In square 2380, receive first sleeve pipe with the first hole.In square 2390, the second sleeve pipe is inserted in the first sleeve pipe, the second sleeve pipe has the second hole that can aim at the first hole, and the first sleeve pipe be configured to rotatable, to the first hole is rotated into the second hole and is aimed at.In square 2400, by balladeur train subassembly and the coupling of flow regulation subassembly.In square 2410, coupling balladeur train subassembly, to control at least partly balladeur train subassembly by the transmitting set-acceptor device that makes the running of reversible electric machine device.In square 2415, finish the method.

In Figure 21 H, a kind of exemplary methods 2420 that assembling is used in the flow control assembly in fission-type reactor is from square 2430.In square 2440, receive flow regulation subassembly.In square 2450, receive first sleeve pipe with the first hole.In square 2460, the second sleeve pipe is inserted in the first sleeve pipe, the second sleeve pipe has the second hole that can aim at the first hole, and the first sleeve pipe be configured to rotatable, to the first hole is rotated into the second hole and is aimed at.In square 2470, by balladeur train subassembly and the coupling of flow regulation subassembly.In square 2480, coupling balladeur train subassembly, to control at least partly balladeur train subassembly by the fiber optic emitter-acceptor device that makes the running of reversible electric machine device.In square 2490, finish the method.

Those skilled in the art will appreciate that parts as herein described (for example, operation), equipment, object and follow their discussion as the example of clarification concept, it is contemplated that out various configuration modification.Therefore, as used herein, the specific examples of displaying and the discussion of following are intended to represent their more general category.In general, the use of any specific examples is all intended to represent its classification, and specific features (for example, operation), 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 representative are as other place in the claims with submitting to herein and/or in the application, in other place is told about herein more general process, equipment and/or technology.

Although shown and described the particular aspects of current theme as herein described, but for a person skilled in the art, obviously, can be according to instruction herein, do not depart from theme as herein described and more broad aspect make change and amendment, therefore, appended claims by as within the true spirit at theme as herein described and scope change and revise the scope that is all included in it within.Those skilled in the art should be understood that, in general, with in this article, especially (be for example used in appended claims, the major part of appended claims) in term as open to the outside world term (be for example generally intended to, gerund term " comprises " that being construed as gerund " includes but not limited to ", and term " has " and is construed as " at least having ", and verb term " comprises " that being construed as verb " includes but not limited to " etc.).Those skilled in the art it is also to be understood that, if having a mind to represent the claim listed item of introducing of specific quantity, will clearly enumerate such intention in the claims, and in the case of lacking such enumerating, does not have such intention.For example, in order to help people to understand, following appended claims may comprise the introductory phrase of use " at least one " and " one or more " and introduce claim listed item.But, for example, even if same claim comprises introductory phrase " one or more " or " at least one " and picture " " or " one " (, " one " and/or " one " should be understood to " at least one " or " one or mores' " the meaning conventionally) such indefinite article, the use of phrase not should be understood to yet and is implying that passing through indefinite article " " or " one " introduces claim listed item and require to be limited in the claim that only comprises such listed item by comprising any specific rights of introducing like this claim listed item like this, for the use of the definite article for introducing claim listed item, this sets up equally.In addition, even if clearly enumerated the claim listed item of introducing of specific quantity, those skilled in the art also should be realized that, enumerating so conventionally should be understood at least there is cited quantity the meaning (for example, in the situation that there is no other qualifier, only enumerate " two listed item " and conventionally mean at least two listed item or two or more listed item).And, be similar in use in those situations of usage of " at least one of A, B and C etc. ", in general, such usage is intended to those skilled in the art and understands in the meaning of this usage and use and (for example, " have at least one the system of A, B and C " and will include but not limited to only have A, only there is B, only there is C, there is together A and B, there is together A and C, there is together B and C, and/or there is together the system of A, B and C etc.).Be similar in use in those situations of usage of " at least one of A, B or C etc. ", in general, such usage is intended to those skilled in the art and understands in the meaning of this usage and (for example use, " there is at least one the system of A, B or C " and will include but not limited to only there is A, only there is B, only there is C, there is together A and B, there is together A and C, there is together B and C, and/or there is together the system of A, B and C etc.).Those skilled in the art it is also to be understood that, conventionally, no matter in description, claims or accompanying drawing, occurring that the separation word of two or more alternative projects and/or phrase should be understood to have comprises one of these projects, any of these projects, or the possibility of two projects, unless context refers else.For example, 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 be carried out by any order.In addition,, although various operating process displays in order, should be understood that various operations can carry out by different from illustrated order other order, or can carry out simultaneously.That the example of alternative like this sequence can comprise is overlapping, interlock, block, reset, increase progressively, prepare, supplement, simultaneously, oppositely or other derivative sequence, unless context refers else.And, as " right ... sensitivity ", " with ... about " or the such term of other past tense adjective be generally not intended to repel so derivative, unless context refers else.

Therefore, the fission-type reactor that provides, flow control assembly, its method and flow control assembly system.

Although herein disclosed is various aspects and embodiment, other side and embodiment are apparent for a person skilled in the art.For example, can replace flow regulation subassembly with horizontally disposed pore plate, pore plate has multiple pores that pass.Multiple corresponding of can activate respectively catch and pore can be associated, pore can be closed and open to these catch gradually, to regulate or adjust to the flow of the cooling medium of nuclear fission module.

In addition, from instruction herein, can understand, from to be disclosed in equipment in above-cited existing patent different, flow control assembly of the present disclosure and system dynamically change the flow of fluid, avoid the difference of the structured material to controlling fluid flow and accurately set neutron bringing out the dependence of growth property, and if can dynamically change during reactor operation if required.

In addition, various aspects 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 (11)

1. be used in fission-type reactor, be configured to the flow control assembly that is connected with fuel assembly, comprise:

(a) adjustable flow regulates subassembly; And

(b) regulate subassembly coupling with described adjustable flow to adjust the balladeur train subassembly of described adjustable flow adjusting subassembly,

Wherein said balladeur train subassembly comprises the long bridge of crossing over described fuel assembly.

2. flow control assembly as claimed in claim 1, wherein said balladeur train subassembly is driven by lead screw device.

3. flow control assembly as claimed in claim 1, wherein said balladeur train subassembly is driven by reversible electric machine device.

4. flow control assembly as claimed in claim 3, wherein said balladeur train subassembly is made transmitting set-acceptor device control of described reversible electric machine device running at least partly.

5. flow control assembly as claimed in claim 3, wherein said balladeur train subassembly is made fiber optic emitter-acceptor device control of described reversible electric machine device running at least partly.

6. be used in fission-type reactor, can with a flow control assembly that is arranged to a selected coupling that is arranged in the multiple nuclear fission fuel assemblies in fission-type reactor, comprise:

(a) the adjustable flow adjusting subassembly of the flow of the fluid stream of selected one of multiple nuclear fission fuel assemblies is flow through in adjustment, and described adjustable flow regulates subassembly to comprise:

(i) there is the outer tube in multiple the first holes; With

(ii) insert the inner sleeve in described outer tube, described inner sleeve has multiple the second holes, variable flow district can be aimed to define with the second hole gradually in the first hole, thereby along with the first hole and the second hole aim to define variable flow district gradually, the fluid stream of variable number flows through the first hole and the second hole; And

(b) regulate subassembly coupling with described adjustable flow to adjust the balladeur train subassembly of described adjustable flow adjusting subassembly,

Wherein said balladeur train subassembly comprises the long bridge of crossing over described fuel assembly.

7. flow control assembly as claimed in claim 6,

(a) wherein said outer tube is generally columniform and rotatable; With

(b) wherein said inner sleeve is generally columniform.

8. flow control assembly as claimed in claim 6, wherein said balladeur train subassembly is driven by lead screw device to rotatably engage with described outer tube.

9. flow control assembly as claimed in claim 6, wherein said balladeur train subassembly is driven by reversible electric machine device to rotatably engage with described outer tube.

10. flow control assembly as claimed in claim 9, wherein said balladeur train subassembly is made transmitting set-acceptor device control of described reversible electric machine device running to rotatably engage with described outer tube at least partly.

11. flow control assemblies as claimed in claim 9, wherein said balladeur train subassembly is made fiber optic emitter-acceptor device control of described reversible electric machine device running to rotatably engage with described outer tube at least partly.