CN103971758A - Nuclear reactor (optional), fuel assembly for seed-blanket subassembly of nuclear reactor (optional) as well as fuel element for fuel assembly - Google Patents
Nuclear reactor (optional), fuel assembly for seed-blanket subassembly of nuclear reactor (optional) as well as fuel element for fuel assembly Download PDFInfo
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- CN103971758A CN103971758A CN201410042725.7A CN201410042725A CN103971758A CN 103971758 A CN103971758 A CN 103971758A CN 201410042725 A CN201410042725 A CN 201410042725A CN 103971758 A CN103971758 A CN 103971758A
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention relates to a fuel element for a fuel assembly of a nuclear reactor. The fuel element comprises a nucleus containinga fissionable material and cladding which seals the nucleus, wherein the fuel element is provided with a multifoil contour which forms spiral ribs; and the spiral ribs comprise the fissionable material and have axially torsional intervals, and the length of each interval is 5%-20% of that of the fuel element. According to embodiments of the invention, waste which can used for manufacturing nuclear weapons cannot be generated, a novel loading and unloading system is used for a first embodiment of the invention tomaximize recycling of fuel in a seed; and the system further guarantees that used nuclear fuel cannot be used for manufacturing nuclear weapons.
Description
The divisional application of the application for a patent for invention that the present invention is that international filing date is that Dec 26, international application no in 2007 are that PCT/RU2007/000732, China national application number are 200780102099.4, denomination of invention is " nuclear reactor (optionally), for the fuel assembly of seed region-renewing zone sub-component of nuclear reactor (optionally) with for the fuel element of fuel assembly ".
Technical field
Present invention relates in general to wherein thorium and design as the light-water reactor of fuel, and be particularly related to the design without chuck fuel assembly of the reactor core that forms for example VVER-1000 of pressurized water reactor (PWR).
Background technology
Nuclear energy is a kind of important energy source in the whole world.The many countries that lack enough local mineral fuel resources all mainly rely on nuclear energy to generate electricity.In many other countries, nuclear energy is as a kind of emulative power supply, and it has also increased the diversity of kind of energy used.In addition, nuclear energy also for example, has been made very important contribution for realizing as control the target that mineral fuel pollute (acid rain and global warming) and preserve mineral fuel for offspring.
Although a subject matter of security yes nuclear reactor designs and operation, another key issue is to can be used for the danger that the material of nuclear weapon increases sharply.This danger is especially relevant to the country that those have unstable government, and the nuclear weapon that they have can cause safely very large threat to the world.Therefore the mode that nuclear energy should increase sharply with the risk that can not cause nuclear weapon and their use to cause is manufactured and uses.
All current nuclear reactors can generate the material that is called as traditionally in a large number reactor-grade plutonium.For example, typical 1000MW reactor can generate about 200-300 kilogram be suitable for making nuclear arms reactor-grade plutonium of device every year.The fuel of therefore discharging from the reactor core of traditional reactor is the material of high diffusion, need to take safety measures to prevent that the fuel of discharging from falling into uncommitted individual's hand.In nuclear weapon unloading process, also there is similar safety problem in the very large stock pile of the weapons grade plutonium generating in the country of the U.S. and USSR (Union of Soviet Socialist Republics).
In the operation of traditional core reactor, also there is the other problem relevant with the quick loss of natural uranium raw-material world supply with disposing the constant needs of long-life radioactive waste.
In order to address these problems, the in the recent period enriched uranium of paid examination application relatively small amount non-proliferation (have 20% or the enriched uranium of the U-235 of less content) and can not generate the nuclear reactor of for example plutonium of a large amount of diffusion materials.The example of this reactor is in open and International Application No. WO 85/01826 and WO93/16477, and they disclose the seed blanket reactor of the quite large number percent the power that regeneration zone from having thorium fuel obtains them.Regeneration zone is around the ignition zone of the fuel rod that comprises non-proliferation enriched uranium.Uranium in seed region fuel rod discharges neutron, and neutron is caught by the thorium in regeneration zone, therefore generates fissionable U-233, and U-233 burns and in position to the heat release of reactor generating plant.
Thorium is attractive as the use of nuclear reactor fuel, because thorium deposit is in the world much larger than uranium reserve.In addition, be no matter the fuel of discharging in the initial fuel loading or in the time that each fuel cycle finishes the meaning of the device that is unsuitable for making nuclear arms, above-mentioned two kinds of reactors are not " non-proliferation ".The realization of this result is by only using non-proliferation enriched uranium as seed region fuel, select moderator/volume of fuel ratio so that plutonium production is reduced to minimum, and add a small amount of non-proliferation enriched uranium to regeneration zone, wherein in the time of the end cycle of renewing zone, U-238 component is mixed equably with residual U-233 and is made U-233 " sex change " (changing its natural characteristic), and consequently it becomes and is unsuitable for the device that makes nuclear arms.
Unfortunately, in above-mentioned reactor design, neither one is real " non-proliferation ".Particularly, have been found that two kinds of designs all cause spreading in ignition zone the production level higher than minimum possibility level of plutonium.There is interior regeneration zone or center regeneration zone and outer peripheral can not be provided as " non-proliferation " reactor reactor operation around the use of the circular ignition zone of regeneration zone, because thin annular ignition zone has quite little " optical thickness ", this has caused seed region (neutron) spectrum, and this spectrum can be arranged the harder spectrum of inner region and regeneration zone.This causes the epithermal neutron of higher proportion in ignition zone and the generation higher than the diffusion plutonium of minimum.
In addition, in previously reactor design, neither one is optimized from the viewpoint of operating parameter.For example, moderator/volume of fuel in ignition zone and regeneration zone is compared to the amount of the plutonium in ignition zone is reduced to minimum especially key, enough like this heat will be discharged by seed region fuel rod, and can ensure in regeneration zone that thorium is to the best transition of U-233.Studies show that the preferred moderator/fuel ratio of indicating is too high and too low in regeneration zone in ignition zone in international application.
In the enriched uranium of the non-proliferation that previous reactor core design consumes equally in seed region fuel element, not very effective.The fuel rod of therefore, discharging in the time that each seed region fuel recycle finishes comprises so many residual uranium and they must be processed again and for reusing at another reactor core.
In application WO93/16477, disclosed reactor also needs complicated automatic reaction heap control system, and this makes it to be unsuitable for ressembling traditional reactor core.Similarly, in application WO85/01826, disclosed reactor core can not be transferred in traditional reactor core easily, because its design parameter and traditional reactor core parameter are incompatible.
Finally, the design of previous reactor be all designed to particularly burn the non-proliferation with thorium enriched uranium and be unsuitable for consuming a large amount of plutoniums.Therefore do not have a kind of design that the solution of the problem of the plutonium of deposit is provided.
According to patent RU2176826, known a kind of reactor with the reactor core that comprises one group of seed region-renewing zone assembly, each seed region-renewing zone assembly all comprises centerfire region, centerfire region comprises the seed region fuel element of making by comprising material that uranium-235 and uranium-238 can nuclear fission, around ignition zone and comprise and mainly comprise thorium and by volume 10% or the annular renewing zone of the blanket element of enriched uranium still less, the volume ratio of the moderator in ignition zone and moderator and fuel is in 2.5 to 5.0 scope, with the moderator in regeneration zone, and moderator with the ratio of fuel in 1.5 to 2.0 scope.Each seed region fuel element is made by U-Zr alloy, and ignition zone forms the 25-40% of the cumulative volume of each seed region-renewing zone module.
Known reactor provides from the optimum operation of economic point of view and has not been " diffusion ".This reactor can be for consuming the plutonium in a large number with thorium the refuse that does not generate diffusion.Reactor can generate substantially the seldom hot waste of amount, and this has reduced the needs to long-term refuse storage significantly.
But the seed region-renewing zone assembly using in reactor is not suitable for for such as VVER-1000 of existing light-water reactor.
From the instructions of patent RU2222837, become known for the fuel assembly of the light-water reactor that is similar to reactor described above, specifically, it has hexagonal cross-section form, and this makes it in traditional light-water reactor, from seed region-renewing zone module, fuel assembly to be installed.
But, except the description of the cross-sectional form to assembly, do not comprise and allow it to be arranged on existing light-water reactor for example in VVER-1000 and do not change the information of the arrangement of components of reactor design for the explanation of above-mentioned patent.
According to the known a kind of fuel assembly for light-water reactor of patent RU2294570, it comprises a branch of fuel element and the guide groove in the grid of interval, empennage and head, wherein, the element that interval grid is connected to each other and is arranged by the length along fuel assembly is connected to empennage, and head is made up of upper padding plate and lower bolster, covering and spring unit between backing plate, and wherein, the external fin on head shell along edge projection and be connected to each other along bottom by perforated plate.
Known fuel assembly is classified as the design for the fuel assembly without chuck, it forms the reactor core of pressurized water reactor (PWR) for example VVER-1000, and due to the free space increasing between the rigidity, the head length reducing and fuel bundle and the head that improve, the simultaneously increase of fuel rod length, therefore has the operating performance of enhancing.Therefore this design can also improve with the fuel load in the larger loss degree of depth raising fuel assembly life cycle of reactor core power and fuel assembly.
But all fuel elements in this assembly are by making for the fissile material of for example VVER-1000 of reactor traditionally; Therefore, the generation of a large amount of reactor-grade plutoniums is the peculiar shortcomings with the reactor of this assembly.
The object of the invention is to create a kind of fuel assembly, fuel assembly can generate sizable number percent of its power and can not generate diffusion refuse in thorium-fuel reproduction region on the one hand, on the other hand, fuel assembly can be arranged on existing light-water reactor for example in VVER-1000 and do not need large variation.
Summary of the invention
The present invention seeks to according to one of embodiments of the invention that fuel assembly by for light-water reactor realizes, this fuel assembly has orthohexagonal form in vertical view, and fuel assembly comprises: seed region sub-component, around the renewing zone sub-component of seed region sub-component, head, empennage and framed structure, it is characterized in that, seed region sub-component comprises a branch of fuel element, wherein each fuel element all has the core being made up of enriched uranium or reactor-grade plutonium, and the covering that described core is made up of zircaloy sealing and there is tri-lobal profile, this tri-lobal profile forms spiral spacer rib, the empennage of seed region sub-component, has installed the fuel element of support grid with holding point flame range sub-component on it, be connected to the groove of the empennage of the seed region sub-component in vertical view with regular hexagon form, and groove is arranged around fuel bundle, guide grids, thus its top that appends to groove allows their free axially-movables for placing fuel element, form guide groove to hold the pipe core of controller, and append to the peripheral tube on support grid, peripheral tube is formed for inserting the guide groove of absorber rod and control rod, and puts into and have the head of elastic shaft to displacement capacity, renewing zone sub-component comprises a framed structure, and this framed structure, by six fore-and-aft tilt cell formations, is provided with interval grid on described six fore-and-aft tilt unit, and has opening in central area to hold the groove of seed region sub-component, be arranged in the fuel element cluster that the thorium by being added with enriched uranium of framed structure forms, empennage with renewing zone sub-component, on it, install the fuel element of renewing zone sub-component, and this empennage can connect with the support column of light-water reactor, and the described empennage of renewing zone sub-component and the empennage of seed region sub-component are connected and are formed the empennage of fuel assembly by locking mechanism.
Head can be equipped with the pressure elements contacting with the groove of seed region sub-component.
In another embodiment of the present invention, the fuel assembly in vertical view with regular hexagon form comprises seed region sub-component, renewing zone sub-component around seed region sub-component, head, the empennage that can connect with the support column of light-water reactor, and framed structure, wherein, seed region sub-component comprises fuel element cluster, each fuel element all has the core being made up of enriched uranium or reactor-grade plutonium, and the covering that described core is made up of zircaloy seals and has tri-lobal profile, and this tri-lobal profile forms spiral spacer rib; The empennage of seed region sub-component, has filled the fuel element of support grid with holding point flame range sub-component on it; Be connected to the groove of the empennage of the seed region sub-component in vertical view with regular hexagon form, and groove is arranged around fuel bundle; Guide grids, allows their free axially-movable thereby this guide grids is installed to the top of groove for placing fuel element; Pipe core and peripheral tube, described pipe core forms guide groove to hold controller, and peripheral tube is formed for inserting the guide groove of absorber rod and control rod, and puts into and have the head of elastic shaft to displacement capacity; Renewing zone sub-component comprises a framed structure, and this framed structure, by six fore-and-aft tilt cell formations, is provided with interval grid on described six fore-and-aft tilt unit, and has opening in central area to hold the groove of seed region sub-component; The fuel element cluster being formed by the thorium that has been arranged in framed structure and has been installed to interpolation on backing plate at bottom (empennage) enriched uranium; With several support columns that append on empennage, and head gear becomes to allow support column to carry out elasticity axial displacement.
In at least one embodiment of the present invention, the zirconium of cross-sectional form or the displacing device of zircaloy that have equilateral triangle mainly arrange to improve the more uniform temperature distribution in this Assessment of Nuclear Volume along the longitudinal axis of core.
In at least one embodiment of the present invention, the axial screw spacing of spiral spacer rib is also in 5% to 20% scope of fuel rod length.
In addition, in at least one embodiment of the present invention, the fuel rod of seed region sub-component has circumference orientation, makes like this tri-lobal profile of any two adjacent fuel rods just have at least one xsect of fuel bundle the common plane of symmetry through the axis of two adjacent fuel elements.
And, in at least one embodiment of the present invention, core is preferably counted by volume the high U-Zr alloy to 30% uranium and is formed by having, and has highly to 20% concentrated U-235 isotope, and core is counted by volume the high Pu-Zr alloy to 30% reactor-grade plutonium and formed by having.
In addition, the object of the invention is a kind of light-water reactor that comprises a group fuel assembly, at least one in fuel assembly is according to structure that one of as mentioned above can arrangement.Put into reactor fuel assembly some or allly can defer to possibility as above.
Brief description of the drawings
Its embodiment by is below together with accompanying drawing, and the features and advantages of the present invention will be apparent, wherein:
Fig. 1 is the schematic cross-sectional diagram of the nuclear reactor that comprises the fuel assembly forming according to this invention;
Fig. 2 is the overall side view according to the fuel assembly of the first embodiment of the present invention, comprising cut-open view;
Fig. 3 be the longitudinal diagram that amplifies show according to the head of the fuel assembly of Fig. 2;
Fig. 4 be the longitudinal diagram that amplifies show according to the empennage of the fuel assembly of Fig. 2;
Fig. 5 is the cut-open view of seed region fuel rod;
Fig. 6 is the A-A cut-open view according to the fuel assembly of Fig. 2;
Fig. 7 is the overall side view according to the fuel assembly of the second embodiment of the present invention, comprising cut-open view;
Fig. 8 be the longitudinal diagram that amplifies show according to the head of the fuel assembly of Fig. 7;
Fig. 9 be the longitudinal diagram that amplifies show according to the empennage of the fuel assembly of Fig. 7.
Embodiment
Fig. 1 has shown the nuclear reactor 1 that comprises a group fuel assembly 2, and fuel assembly 2 comprises ignition zone and regeneration zone, and fuel assembly 2 forms hexagon-shaped configuration, and wherein fuel assembly is from have orthohexagonal form in vertical view.Reactor core 1 has identical geometric configuration and size with the reactor core of traditional VVER-1000 light-water reactor, and reactor will be ressembled this assembly to form the reactor core of 163 fuel assemblies 2 like this.Reactor core 1 and the difference of the reactor core of VVER-1000 reactor are component and the structure of fuel assembly 2, as below announce in more detail.The reactor core 1 providing at this and fuel assembly 2 have been developed for traditional VVER-1000 light-water reactor; But, can generate similar reactor core and fuel assembly and not exceed scope of the present invention for the reactor of other standard or particular design.
Reactor core 1 by reverberator 3 around, reverberator 3 preferably includes one group of reflector assembly 4.Each reflector assembly 4 all preferably comprises reactor core cage (the basket)/water of high pressure vessel and the potpourri of metal.In addition, easy reflector assembly 4 can mainly be made up of thoria.
Fig. 2 has shown total figure that can arrangement for first of each fuel assembly 2.
Fuel assembly 2 comprises seed region sub-component 5, renewing zone sub-component 6, head 7 and empennage 8 around seed region sub-component 5, and the support section 9 of empennage 8 contacts with the support column of reactor (not shown).Fuel assembly has orthohexagonal form in vertical view.Seed region sub-component 5 comprises fuel bundle 10, and fuel bundle 10 comprises multiple for example 108 rods that are placed on support grid 11, and support grid 11 is connected to the empennage of seed region sub-component 5.The groove 12 with hexagonal cross-section is connected to the empennage of seed region sub-component 5 and surrounds fuel bundle 10.Thereby allow the guide grids 13 of their free axially-movables to be connected to the top of groove 12 for placing fuel element 10.Each seed region fuel element all has core 14, and core 14 comprises enriched uranium or reactor-grade plutonium.Core is mainly made up of U-Zr alloy, and has in fuel element meter by volume and account for 25% or lower uranium concentration and 19.7% enriched uranium-235.Core 14 is sealed and tool tri-lobal profile by the covering 15 of zircaloy, and this tri-lobal profile forms spiral spacer rib 16(Fig. 5).The zirconium of xsect or the displacing device of zircaloy 17 with equilateral triangle form are arranged along the longitudinal axis of core.Seed region fuel rod 10 can be fabricated to single assembly parts by combination of extrusion (by the extruding of mould).The axial screw spacing of spiral spacer rib 16 is to choose according to the situation of axis of placing adjacent fuel rod 10, and interval equals to stride across the width in the corner in the xsect of fuel rod and be 5% to 20% of fuel rod length.The stability of the portrait configuration of fuel rod 10 is provided by following parts: provided by support grid 11 in bottom; Provided by guide grids 13 at top; With respect to the height of reactor core be by the height with respect to fuel bundle equably the band system (not shown) of interval in groove provide.Seed region fuel element 10 has circumference orientation, makes like this tri-lobal profile of any two adjacent fuel rods just have the common plane of symmetry, this plane of symmetry at least one cross section of fuel bundle through the axis (Fig. 5) of two adjacent fuel elements.
In addition, seed region sub-component comprises formation guide groove to hold the pipe core 18 and the peripheral tube 19 that is connected to support grid 13 of controller, and peripheral tube 19 forms guide groove for inserting based on boron carbide (B
4and metatitanic acid dysprosium (Dy C)
2o
3tiO
2) control absorber elements (not shown) and based on boron carbide and gadolinium oxide (Gd
2o
3) flammable absorber rod (not shown), and be placed in the head 7 with elasticity axial displacement.The peripheral tube 19 that forms guide groove is made by zircaloy.
Head 7(Fig. 3) formed by Flexible element, Flexible element comprises pre-compressed spring 20, upper board 21, covering 22 and lower panel 23.Covering 22 collapses part by two and forms, and, is connected to rigidly the top 24 of upper board 21 that is, and is connected to rigidly the bottom 25 of lower panel 23.Flexible element comprises the spring 20 that is arranged in covering 22 inside.Peripheral tube 19 is assembled in sleeve 26 and can acts on (for example,, owing to having step on the outside surface at pipe 19) on the bottom of sleeve.Sleeve 26 has flange, and the Compress Spring 20 of Flexible element is resisted against on this flange.Other end of spring 20 is resisted against on upper board 21.The upper end of pipe 19 is freely through the through hole in upper board 21, and sleeve 26 is through the opening in lower panel 23.Pipe 19 has backstop 27 on top.Pipe core 18 is to install with the similar mode of peripheral tube 19, and difference is that it does not freely use sleeve through lower panel.The spring 20 being passed by pipe core 18 is directly resisted against in the lower panel 23 of head 7.The strut 28 in upper end with backstop 29 is connected to lower panel 23 with the distance between confinement plate 21 and 23; Strut 28 is freely through the opening in upper board 21.The pressure elements 30 contacting with the groove 12 of seed region sub-component 5 is connected to lower panel 23.Therefore the load that is applied to upper board 21 in the time that groove 12 is fixed to prevent axially-movable is via peripheral tube 19 and be directly passed to support grid 11 by groove 12.
Head can be configured to does not have sleeve 26.In this case, all springs 20 of spring unit are just resisted against in lower panel 23, and peripheral tube 19 is freely through the opening (being similar to pipe core 18) mating in lower panel 23.The whole load that is applied to upper board 21 in the time that groove 12 is fixed to prevent from moving is directly passed to support grid 11 by groove 12.
The empennage of seed region sub-component 5 has the locking device 31 that is connected to housing, it comprise have opening 33 cylindrical wall 32, put into the ball 34 of opening and there is ring groove 36 and the locking member 35 that can carry out axially-movable.Provide the locking device 31 being connected between seed region sub-component 5 and the empennage 37 of renewing zone sub-component also can form with any other form; Only importantly it provides the dismountable connection of empennage of seed region sub-component and renewing zone sub-component.
Renewing zone sub-component 6 comprises framed structure 38, is arranged in fuel bundle 39 and the empennage 40 of framework.
Framed structure 38 is made up of six fore-and-aft tilt unit 41, and interval grid 42 is connected on described fore-and-aft tilt unit by resistance spot welding.Each interval grid 42 is honeycomb grid, forms one group of unit (specifically 228) that is connected to edge with outer-hexagonal and interior hexagonal.Interval grid 42 provides the requisite space of fuel rod 39 and the Len req contacting with them to allow fuel rod 39 to slide in the grid cell of interval when length expansion due to radiation and heat at them, provide the possible sliding force of minimum of fuel rod to reduce the internal stress in fuel bundle, and provide required initial compactness to avoid fuel element fretting corrosion during operation.Interval grid 42 has opening to hold the groove 12 of seed region sub-component 5 in central area.
Tilting unit is connected to the empennage 40 of renewing zone sub-component 6 rigidly in bottom, connected the support grid 43 of renewing zone sub-component to keep fuel rod 39 on it.The support grid 43 of renewing zone sub-component 6 provides under the pattern of normal running (operation) conditions, has violated the physical strength under load under the pattern of normal running (operation) conditions and in design accident, and provides according to calculating required fluid resistance.
The fuel bundle 39 of renewing zone sub-component comprises one group of fuel element (specifically 228 elements), and this fuel element is by comprising by volume 12% UO
2by volume 88% ThO
2component make and to have 19.7% U-235 concentrated.
The volume V of all fuel elements of seed region sub-component
seedvolume V with all fuel elements of renewing zone sub-component
blankratio be approximately 0.72.
The empennage 40 of renewing zone sub-component 6 comprises support grid 43, housing 44 and ring 46, and bracket 45 is connected to described ring 46 rigidly; Ring interacts with locking device 31.The end of blanket element 39 is connected to support grid 43.Support grid 43 provides under the pattern of normal running (operation) conditions, has violated the physical strength under load under the pattern of normal running (operation) conditions and in design accident, and the required fluid resistance flowing to cooling medium (water) is provided.Housing 44 can combine with the support column (not shown) of light-water reactor and serve as the guiding device to the region of seed region sub-component and renewing zone sub-component by coolant feed.
Fig. 7-9 have shown the second possibility of the structure of each fuel assembly 2.
This optional design is that with the difference of design shown in Fig. 2-4 seed region sub-component and renewing zone sub-component are not connected each other rigidly.As shown in Figure 9, the empennage of seed region sub-component has cylindrical bottom portion backing plate 47 and replaces locking device 31, and housing 44 in the empennage 40 of renewing zone sub-component 6 lacks the bracket 45 shown in Fig. 4 and ring 46.Compared with pattern shown in Fig. 3, covering 22(Fig. 8 of head 7) form an entirety, and additional spring unit 48 connects (for example, welding) rigidly to above it.Additional spring unit 48 mainly comprises several (for example, six) around even circumferential distribute and be connected to rigidly the additional upper board 49 of covering 22, be connected to rigidly the additional lower panel 50 of lower panel 23, the covering 51 that is connected to additional upper board 49 and lower panel 50, Compress Spring 52 and support column 53.Support column 53 is connected to the support grid 43 of renewing zone module 6 by bottom.The top of support column 53 is similar to peripheral tube 19 and forms and be placed in additional upper board 49 and lower panel 50; , support column 53 is assembled in sleeve 26 and can acts on sleeve along upward direction.The Compress Spring 52 of additional spring unit 48 is at one end resisted against on the flange of sleeve 26 and is resisted against on additional upper board 21 at the other end.The top of support column 53 is freely through the through hole in additional upper board 49, and sleeve 26 is through the opening in additional lower panel 50.Support column 53 has backstop 54 on top.
Before fuel assembly is put into reactor, first seed region sub-component 5 and renewing zone sub-component 6 are assembled individually.
In the assembling of the seed region sub-component according to the first embodiment, fuel element 10 is connected to the guide grids 13 installing on groove 12, and pipe core 18 and peripheral tube 19 are also connected to head except being connected to guide grids 13.Pipe core 18 and peripheral 19 through being arranged in lower panel opening sleeve 17, by the through hole of spring 20 and upper board 21.Then backstop 27 is attached to the top (for example,, by threaded joint or bayonet coupling) of pipe.
The fuel element 39 of renewing zone sub-component is placed in framed structure 9 by making them through interval grid 42 and they being attached to support grid 43.
Then,, by making the groove 12 of seed region sub-component 5 through the opening in the core of interval grid 42, the seed region sub-component of assembling is connected to form single subassembly with renewing zone sub-component.These openings mate with the shape of cross section of groove 12 in the configuration of the core of interval grid 42, and groove 12 just can freely pass opening like this.Locking member 35 in the empennage of seed region sub-component moves up, and the ball 34 that is arranged in like this opening 33 of cylindrical wall 32 just can, in ring groove 36 motions, therefore allow cylindrical wall 32 through ring 46.After the empennage of seed region sub-component rests on the upper surface of encircling 46, locking member 36 can move down.Ball 34 is forced to leave groove 36, outwards mobile and outstanding from wall 32 from opening 33.Therefore,, due to the interaction of the ball of displacement and the bottom face of ring 46, the empennage of seed region sub-component can not move up with respect to the empennage of renewing zone sub-component.Therefore seed region sub-component and renewing zone sub-component form single subassembly 2.
Put into after reactor 1 and empennage 8 be placed on the support column (not shown) of light-water reactor at fuel assembly 2, fuel assembly 2 is maintained by being resisted against on the face of covering of upper board 21 of head 7 by the upper board of reactor (not shown).Then force transmission is to the spring unit with spring 20, and this spring unit is compressed, and decrement is designed to prevent that fuel assembly 2 from floating from the coolant flow of below; The upper board 21 of head 7 moves down the decrement of spring unit with respect to lower panel 23.The possibility that upper board 21 moves downward with respect to the lower panel 23 of head 7 is that top 24 by making covering 22 and the flexible of bottom 25 of covering 22 provide, wherein, top 24 is connected to upper board 21 rigidly, and bottom 25 is connected to lower panel 23 rigidly.
Then, acting force from the bottom of the spring 20 of spring unit acts on peripheral tube 19 by their bottom of sleeve 26() be passed to peripheral tube 19, then be passed to support grid 11 and the empennage by seed region sub-component, locking device 31, ring 46 and bracket 45, thereby be passed to the empennage 44 of the renewing zone sub-component 6 contacting with the support column (not shown) of light-water reactor.
In addition, by making blocked center pipe 18 and being directly resisted against its Bonding pressure element 30 rigidly of described lower panel 23() on the acting force of spring 20 act on pressure elements 30, the pressure that part is carried out the upper board of autothermal reactor is passed to the groove 12 of seed region sub-component.If head 7 does not have sleeve 26, all pressure just transmits via groove 12.
Cooling medium enters fuel assembly 2 by the housing 44 of the empennage of renewing zone sub-component 6; Coolant flow is divided into two parts, one of them housing 12 internal flow at seed region sub-component and immersion seed region fuel element 10, and another part is at the flows outside of housing 12 and the fuel element 39 of immersion renewing zone sub-component.
Prevent that from the pressure of the head 7 of the upper board effect of reactor (not shown) fuel element from floating the coolant flow of specifying.
Coolant flow is at the lower crossing point flame range sub-component of the nominal pressure gradient (for existing VVER-1000 reactor) of the height with respect to fuel assembly and the required passage (for extracting rated power from fuel assembly) of renewing zone sub-component and keep the availability of assembly to provide in the following way:
-by use groove 12 between seed region sub-component and renewing zone sub-component;
-by seed region fuel element 10(tri-lobal profile) shape, their mutual circumference orientation and the axial screw spacing of spiral spacer rib 16, this has promoted to form better heat-transfer area and has distributed because the forced convertion of cooling medium mixes the more uniform coolant temperature in the xsect of seed region sub-component causing.
In fact whole hydraulic characteristics of fuel assembly 2 conform to the characteristic of Standard fuel assembly, and this has ensured use to maintain in nominal level according to the resistance of the reactor core of the VVER-1000 reactor of fuel assembly of the present invention.Therefore, the variation that can not cause coolant flow in the major loop of reactor according to fuel assembly of the present invention is installed in VVER-1000.
When fuel element 10 heating during operation of seed region sub-component, can expand and starts upwards prolongation due to thermal expansion and radiation; Fuel element cluster can be independent of peripheral tube 19 and expand, because peripheral tube passes the unit of guide grids 13 with the gap ensureing.Therefore their distortion are carried with peripheral tube 19 and can not made in the Shu Buhui of fuel element 10 impact; Therefore, can keep during operation the geometrical stability of fuel assembly 2 forms.
The fuel element 39 of renewing zone sub-component during operation can be because radiation is expanded and expanded in length and start to occupy the free space between their end and head 7.
Operation according to the fuel assembly 2 of the second embodiment of the present invention is similar, difference is that the housing 44 of renewing zone sub-component is pressed in the support column of reactor through the transmission of support column 53 from the upper board of reactor by pressure, and transmit the effect on the flange of sleeve 26 of power by spring 20 at the support grid 11 to seed region sub-component, can prevent that the seed region sub-component that is not connected to renewing zone sub-component from floating.
Due to the existence of thorium part (renewing zone sub-component) in fuel assembly design, use of the present invention can realize the saving of natural uranium, because in loss process, thorium can gather the auxiliary kernel fuel of uranium-233 form, and the burning meeting of auxiliary kernel fuel is made sizable contribution to the power stage of the reactor core with this fuel assembly.This causes the improvement in non-proliferation characteristic and has simplified the problem of having used in fuel assembly of processing, because for traditional auxiliary kernel fuel (reactor-grade plutonium of VVER-1000 reactor, can be used for the device that makes nuclear arms) can reduce significantly (reducing 80%), and new auxiliary kernel fuel uranium-233(or more accurately, remaining after " locality " burning in the module of thorium renewing zone) can due to uranium-232 isotope even plutonium isotopic pollution and cannot be for the manufacture of nuclear weapon.The isotopic content in cycle rated life time of fuel and the fuel of minimizing discharge by improving with long-term radiotoxicity reduces refuse volume, can simplify the problem in the processing of having used fuel assembly.
Can use the fuel assembly in VVER-1000 reactor according to fuel assembly of the present invention design, this be due to the design of Standard fuel assembly in machinery, hydraulic pressure and neutron compatibility compatible mutually.
With the machinery compatibility of the Standard fuel assembly for VVER-1000 reactor by following guarantee:
-the existence of the framed structure of resistance to deformation power under long period of operation and high fuel consumption level;
-identical size for connection;
-with the use of empennage, head and the framework design of the appropriate section compatibility of turning formula Standard fuel assembly;
The compatibility of the design of-seed region sub-component and standard control gear and load treatment facility.
Owing to being formed with renewing zone sub-component by seed region sub-component and by common distribution (conveying) and the existence of system of collecting two parallel slots being connected of collector, in fact conforming to the characteristic of Standard fuel assembly according to whole hydraulic characteristics of fuel assembly of the present invention.Seed region sub-component is hydraulically connected in entrance and exit section with renewing zone sub-component.This fuel assembly structure ensures to use and according to fuel assembly of the present invention, the resistance of the reactor core of VVER-1000 reactor is maintained in nominal level.Therefore, the variation that can not cause coolant flow in the major loop of reactor according to fuel assembly of the present invention is installed in VVER-1000 reactor.According to fuel assembly of the present invention and Standard fuel assembly, fluid resistance ratio between the outlet of the active part of assembly entrance, renewing zone sub-component and assembly is similar, and this has ensured not exist cooling medium to overflow according between the hydraulic pressure compatibility of fuel assembly of the present invention and standard package and they.
This just can use some this reactor to be used to Standard fuel assembly according to fuel assembly of the present invention in reactor simultaneously.
Provided by following with the neutron compatibility of Standard fuel assembly:
-by utilizing special fuel component and thering is the appointment level that burnouts that the component of flammable absorber realizes;
-be carried in the calibration power output of the fuel assembly that the specific part of the fuel in seed region and renewing zone fuel element realizes by utilization;
-be carried in the specific part of the fuel in each row seed region rod and be carried in the component of the fuel in renewing zone by utilization, realize the meeting of requirement of the uneven distribution to power stage;
-by utilizing the property of fuel element to realize the maintenance for reaction effect in the typical scope of Standard fuel assembly;
-by utilize standard technology groove and for the peripheral tube of the seed region sub-component of seed region sub-component compatibility in guide control rod, realized the ability that uses standard control system regulation output level and reduce output.
Another advantage of the present invention is capable of being combined according to seed region-renewing zone of the present invention fuel assembly, and this can change seed region sub-component independently.Change more continually seed region sub-component and can generate more favourable situation (for neutron balance and radiated time) for putting into the thorium of renewing zone sub-component of fuel assembly.
Claims (11)
1. for a fuel element for the fuel assembly of nuclear reactor, described fuel element comprises:
The core that comprises the material that can fission; And
Seal the covering of described core,
Wherein, described fuel element has the multi-leaf-shaped profile that forms spiral ribs, and wherein, described spiral ribs comprises the material that can fission,
Wherein, described spiral ribs have the length of described fuel element 5% and 20% between the spacing of axial torsion.
2. fuel element as claimed in claim 1, wherein, described covering comprises zircaloy.
3. fuel element as claimed in claim 1 or 2, wherein, described core comprises to have counts 30% or the U-Zr alloy of uranium still less by volume, and described uranium is concentrated by uranium isotope U-235 until 20% or still less.
4. the fuel element as described in any one in claims 1 to 3, wherein, described core comprises to have counts 30% or the Pu-Zr alloy of reactor-grade plutonium still less by volume.
5. the fuel element as described in any one in claim 1 to 4, wherein, described fuel element comprises by mould and pushes the fuel element that extrudes forming.
6. the fuel element as described in any one in claim 1 to 5, also comprise the center displacing device extending along the longitudinal axis of described fuel element, described displacing device comprises along the outward extending multiple projections of side direction, and described core stretches out along side direction from described displacing device
Wherein, each projection is correspondingly aimed at each spiral ribs.
7. fuel element as claimed in claim 6, wherein, each projection and their respective rib have the twist matching along their longitudinal axis.
8. the fuel element as described in claim 6 or 7, wherein, in the xsect perpendicular to longitudinal axis of described fuel element, described core is around described displacing device.
9. the fuel element as described in any one in claim 6 to 8, wherein, multiple ribs comprise along the isolated rib in even circumferential ground, and wherein, the shape of cross section of described displacing device is regular polygon, this polygonal each bight is for each rib.
10. the fuel element as described in any one in claim 6 to 9, wherein, multiple ribs comprise that three along the isolated rib in even circumferential ground, and wherein, the shape of cross section of described displacing device is equilateral triangle, aligns with the leaf of described core in the summit of described equilateral triangle.
11. fuel elements as described in any one in claim 6 to 10, wherein, described displacing device comprises zirconium or zircaloy.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410042725.7A CN103971758B (en) | 2007-12-26 | 2007-12-26 | For the fuel element of fuel assembly |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN200780102099.4A CN101911211B (en) | 2007-12-26 | 2007-12-26 | Nuclear reactor (variants), fuel assembly consisting of driver-breeding modules for nuclear reactor (variants) and fuel cell for fuel assembly |
| CN201410042725.7A CN103971758B (en) | 2007-12-26 | 2007-12-26 | For the fuel element of fuel assembly |
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| CN200780102099.4A Division CN101911211B (en) | 2007-12-26 | 2007-12-26 | Nuclear reactor (variants), fuel assembly consisting of driver-breeding modules for nuclear reactor (variants) and fuel cell for fuel assembly |
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| CN103971758B CN103971758B (en) | 2017-06-23 |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104183279A (en) * | 2014-08-26 | 2014-12-03 | 南华大学 | Inner-cooling pressurized-water reactor core |
| CN106716546A (en) * | 2014-09-16 | 2017-05-24 | 光桥公司 | Nuclear fuel assembly |
| CN112071441A (en) * | 2020-08-10 | 2020-12-11 | 岭东核电有限公司 | Novel fuel assembly with spiral structure fuel rod |
Family Cites Families (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3335060A (en) * | 1965-09-20 | 1967-08-08 | Richard L Diener | Seed-blanket neutronic reactor |
| US3957575A (en) * | 1974-04-16 | 1976-05-18 | The United States Of America As Represented By The United States Energy Research And Development Administration | Mechanical design of a light water breeder reactor |
| US5737375A (en) * | 1994-08-16 | 1998-04-07 | Radkowsky Thorium Power Corporation | Seed-blanket reactors |
| RU2246142C1 (en) * | 2003-05-30 | 2005-02-10 | Фгуп Окб "Гидропресс" | Nuclear reactor fuel assembly (alternatives) |
-
2007
- 2007-12-26 CN CN201410042725.7A patent/CN103971758B/en active Active
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104183279A (en) * | 2014-08-26 | 2014-12-03 | 南华大学 | Inner-cooling pressurized-water reactor core |
| CN106716546A (en) * | 2014-09-16 | 2017-05-24 | 光桥公司 | Nuclear fuel assembly |
| CN112071441A (en) * | 2020-08-10 | 2020-12-11 | 岭东核电有限公司 | Novel fuel assembly with spiral structure fuel rod |
| CN112071441B (en) * | 2020-08-10 | 2021-09-07 | 岭东核电有限公司 | Fuel assembly with fuel rod of helical structure |
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| Publication number | Publication date |
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| CN103971758B (en) | 2017-06-23 |
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