CN117976255A - Lead-based fast reactor core based on annular fuel element - Google Patents
Lead-based fast reactor core based on annular fuel element Download PDFInfo
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- CN117976255A CN117976255A CN202311874075.8A CN202311874075A CN117976255A CN 117976255 A CN117976255 A CN 117976255A CN 202311874075 A CN202311874075 A CN 202311874075A CN 117976255 A CN117976255 A CN 117976255A
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- 239000000446 fuel Substances 0.000 title claims abstract description 217
- 238000005253 cladding Methods 0.000 claims abstract description 27
- 239000008188 pellet Substances 0.000 claims abstract description 24
- 239000000110 cooling liquid Substances 0.000 claims abstract description 15
- 239000002826 coolant Substances 0.000 claims abstract description 14
- 238000001816 cooling Methods 0.000 claims abstract description 9
- 230000000712 assembly Effects 0.000 claims description 22
- 238000000429 assembly Methods 0.000 claims description 22
- 239000000463 material Substances 0.000 claims description 17
- 229910052580 B4C Inorganic materials 0.000 claims description 12
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 claims description 12
- 229910052797 bismuth Inorganic materials 0.000 claims description 8
- JCXGWMGPZLAOME-UHFFFAOYSA-N bismuth atom Chemical compound [Bi] JCXGWMGPZLAOME-UHFFFAOYSA-N 0.000 claims description 8
- 230000009257 reactivity Effects 0.000 claims description 6
- 229910001338 liquidmetal Inorganic materials 0.000 claims description 5
- 238000011160 research Methods 0.000 description 7
- 238000013461 design Methods 0.000 description 6
- FLDALJIYKQCYHH-UHFFFAOYSA-N plutonium(IV) oxide Inorganic materials [O-2].[O-2].[Pu+4] FLDALJIYKQCYHH-UHFFFAOYSA-N 0.000 description 6
- 238000011161 development Methods 0.000 description 4
- 238000012546 transfer Methods 0.000 description 4
- 230000009286 beneficial effect Effects 0.000 description 3
- 230000003750 conditioning effect Effects 0.000 description 3
- 230000035755 proliferation Effects 0.000 description 3
- 238000004458 analytical method Methods 0.000 description 2
- 230000010485 coping Effects 0.000 description 2
- 238000009826 distribution Methods 0.000 description 2
- 230000017525 heat dissipation Effects 0.000 description 2
- 238000005457 optimization Methods 0.000 description 2
- 238000005192 partition Methods 0.000 description 2
- 230000002035 prolonged effect Effects 0.000 description 2
- 229910001220 stainless steel Inorganic materials 0.000 description 2
- 239000010935 stainless steel Substances 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 239000006096 absorbing agent Substances 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 238000000576 coating method Methods 0.000 description 1
- 238000002485 combustion reaction Methods 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000003912 environmental pollution Methods 0.000 description 1
- 239000002360 explosive Substances 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 230000004907 flux Effects 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 239000003607 modifier Substances 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 238000001228 spectrum Methods 0.000 description 1
- 239000013589 supplement Substances 0.000 description 1
- WFKWXMTUELFFGS-UHFFFAOYSA-N tungsten Chemical compound [W] WFKWXMTUELFFGS-UHFFFAOYSA-N 0.000 description 1
- 229910052721 tungsten Inorganic materials 0.000 description 1
- 239000010937 tungsten Substances 0.000 description 1
Classifications
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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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- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The application discloses a lead-based fast reactor core based on an annular fuel element, which comprises a fuel area, a reflecting area and a shielding area, wherein the reflecting area surrounds the fuel area, and the shielding area surrounds the reflecting area; the fuel zone comprises a fuel inner zone and a fuel outer zone which are internally and externally divided, the fuel zone is provided with a plurality of component positions, gaps among the component positions are cooling channels, and the cooling channels are filled with cooling liquid; the fuel assembly is arranged at the position of part of the assembly and comprises a plurality of fuel elements, the fuel elements comprise fuel pellets and fuel core cladding which wraps the fuel pellets, and the section of the fuel elements is annular, so that the inner side and the outer side of the fuel pellets can take away heat through a coolant; an adjusting component is arranged at the position of part of the components, and can move up and down at the position of the components; a safety component is arranged at the position of part of the components, and the safety component can move up and down at the position of the components. The application can realize the combination of the annular fuel element and the lead-based fast reactor core.
Description
Technical Field
The invention relates to the technical field of nuclear reactors, in particular to a lead-based fast reactor core based on an annular fuel element.
Background
The development of nuclear energy technology is one of the main problems in the current age, and is an important means for solving the problems of world resource shortage, environmental pollution and the like, and the design and optimization of nuclear reactors are not separated.
At present, a nuclear energy system has been developed to the fourth generation, wherein a lead-based fast reactor has the advantages of low requirements on operation conditions, difficult generation of explosive gas in the operation process, harder energy spectrum, realization of fuel proliferation by effectively converting fissionable nuclides into fissionable nuclides, and the like, and is considered as a reactor with the most development prospect.
International research work on lead-based fast stacks has progressed, with most stacks still in the development stage and the rest in the conceptual design stage. The conventional lead-based fast reactor mostly adopts a fuel element with a rod-shaped or plate-shaped structure. However, the rod-shaped fuel has high highest temperature, poor heat dissipation and low safety due to the fact that the center of the fuel pellet is far away from the cladding, and the plate-shaped fuel element has various sizes due to the special shape, so that the complexity of manufacturing is increased. Therefore, further research is still needed in the search and optimization of fuel element structures to improve lead-based fast reactor economy and safety.
The annular fuel element not only can reduce the highest fuel temperature at the same power level and provide higher safety margin, but also can improve the minimum critical heat flux ratio and the fuel utilization rate, and can also improve the output power of the reactor core under the condition that the safety margin is kept unchanged. However, most of the research on annular fuel elements is on the level of their own characteristics and concepts, and the annular fuel and the core are rarely designed integrally, and the existing core design based on annular fuel elements is mainly focused on water-cooled stacks or small stacks. The annular fuel element has great development potential in optimizing the performance of lead-based fast stacks.
Disclosure of Invention
The present invention aims to solve, at least to some extent, one of the above technical problems in the prior art. Therefore, the embodiment of the invention provides the lead-based fast reactor core based on the annular fuel element, which realizes the combination of the annular fuel element and the lead-based fast reactor core and has the characteristics of long service life, excellent safety and high fuel utilization rate.
The lead-based fast reactor core based on the annular fuel element comprises a fuel area, a reflecting area and a shielding area, wherein the reflecting area surrounds the fuel area, and the shielding area surrounds the reflecting area; the fuel zone comprises a fuel inner zone and a fuel outer zone which are internally and externally divided, the fuel zone is provided with a plurality of component positions, gaps among the component positions are cooling channels, the cooling channels are filled with cooling liquid, and the cooling liquid is liquid metal lead bismuth; a fuel assembly is arranged at part of the assembly position, the fuel assembly comprises a plurality of fuel elements, the fuel elements comprise fuel pellets and a fuel core cladding which wraps the fuel pellets, the section of the fuel elements is annular, so that both the inner side and the outer side of the fuel pellets can take away heat through the coolant; an adjusting assembly is arranged at part of the assembly positions and used for adjusting the reactivity of the lead-based fast reactor core based on the annular fuel element so that the lead-based fast reactor core based on the annular fuel element is critical in steady-state operation, and the adjusting assembly can move up and down at the assembly positions; and part of the assembly positions are provided with safety assemblies for implementing shutdown operation, the safety assemblies can move up and down at the assembly positions, and the space left by the single safety assemblies after moving is filled with coolant.
In an alternative or preferred embodiment, the positions of the components are arranged layer by layer from the center of the fuel inner area to the outer ring of the fuel outer area and are arranged in a honeycomb shape, the adjusting components are dispersed at the junction of the fuel inner area and the fuel outer area and at the middle position of the fuel inner area, and the safety components are uniformly dispersed in the area of the fuel area.
In an alternative or preferred embodiment, the fuel assembly has a hexagonal prism shape, and the fuel assembly includes a fuel housing in which the fuel elements are disposed, and a first flow passage for the coolant fluid is provided between each of the fuel elements in the fuel housing.
In an alternative or preferred embodiment, in the fuel element, a first air cavity is arranged between the fuel pellet and the fuel core cladding, and the upper end and the lower end of the fuel pellet are respectively provided with a first air cavity section, a first reflection section and a first shielding section in sequence.
In an alternative or preferred embodiment, the fuel pellets are made of MOX fuel, wherein 93% UO2+7% PuO2 is used in the inner fuel region and 88.3% UO2+11.7% PuO2 is used in the outer fuel region. By adopting MOX fuel partition arrangement, the enrichment degree of U235 in and out of the fuel is the same, but the ratio of UO2 to PuO2 is different, and the ratio of PuO2 in and out of the fuel to MOX fuel is 7% and 11.7% respectively, so that fissionable nuclide U238 can be fully utilized to realize fuel proliferation, and the flattening of power in a reactor is facilitated. By adopting the technical scheme, the reactor core refueling cost can be reduced, and the service life of the reactor core can be prolonged.
In an alternative or preferred embodiment, the adjusting assembly is cylindrical, the adjusting assembly comprises a first guide pipe and a plurality of adjusting elements arranged in the first guide pipe, and a second flow passage for the cooling liquid to circulate is arranged between each adjusting element in the adjusting assembly.
In an alternative or preferred embodiment, the adjusting element comprises an adjusting rod and an adjusting rod cladding which wraps the adjusting rod, a second air cavity is formed between the adjusting rod and the adjusting rod cladding, the adjusting rod is made of boron carbide material, and a second reflecting section, a second air cavity section and a second shielding section are sequentially arranged at the upper end of the adjusting rod.
In an alternative or preferred embodiment, the safety assembly is cylindrical, the safety assembly comprises a second guide tube and a plurality of safety elements arranged in the second guide tube, and a third flow passage for the cooling liquid is arranged between each safety element in the safety assembly.
In an alternative or preferred embodiment, the safety element comprises a safety rod and a safety rod cladding for wrapping the safety rod, a third air cavity is arranged between the safety rod and the safety rod cladding, the safety rod is made of boron carbide material, and two ends of the safety rod are respectively provided with a load bearing material.
In an alternative or preferred embodiment, the fuel inner zone is provided with 217 component positions, the fuel inner zone has 10 component positions for placing the adjustment component or the safety component, the fuel outer zone is provided with 180 component positions, and the fuel outer zone has 28 component positions for placing the adjustment component or the safety component.
Based on the technical scheme, the embodiment of the application has at least the following beneficial effects: according to the technical scheme, in order to ensure the safety of the reactor core and reduce the possibility of rod clamping accidents of the reactor core, two sets of control systems, namely the adjusting component and the safety component, are adopted in the fuel zone, wherein the adjusting component is used for adjusting the reactivity of the reactor core to enable the reactor core to be critical in steady-state operation, the safety component is used for coping with emergency shutdown, refueling and other conditions, and the two sets of control systems can independently mediate the reactor to ensure that the reactor is safe in operation or failure. Moreover, the fuel element adopts an annular design, and the heat can be taken away by the coolant on the inner side and the outer side of the fuel element due to the special structure of double-sided cooling. The liquid metal lead bismuth is adopted as the coolant, so that the coolant has higher heat transfer coefficient compared with water, and the heat transfer capacity and the safety of the reactor core are obviously improved. The application combines the annular fuel element with the lead-based fast reactor core, has the characteristics of long service life, excellent safety, high fuel utilization rate and the like, can be used as a power reactor for providing electric energy, can be used as a research reactor for carrying out analysis and research works such as the performance of a related fast neutron breeder, and provides reference value for optimizing the structure of the follow-up fast breeder.
Drawings
The invention is further described below with reference to the drawings and examples;
FIG. 1 is a radial cross-sectional view of an embodiment of the present invention;
FIG. 2 is a radial cross-sectional view of a fuel assembly in an embodiment of the invention;
FIG. 3 is a radial cross-sectional view of a fuel element in an embodiment of the invention;
FIG. 4 is an axial cross-sectional view of a fuel element in an embodiment of the invention;
FIG. 5 is a radial cross-sectional view of an adjustment assembly in an embodiment of the invention;
FIG. 6 is a radial cross-sectional view of an adjustment element in an embodiment of the invention;
FIG. 7 is an axial cross-sectional view of an adjustment member in an embodiment of the invention;
FIG. 8 is a radial cross-sectional view of a safety assembly in an embodiment of the invention;
FIG. 9 is a radial cross-sectional view of a security element in an embodiment of the invention;
figure 10 is an axial cross-sectional view of a security element in an embodiment of the invention.
Detailed Description
Reference will now be made in detail to the present embodiments of the present invention, examples of which are illustrated in the accompanying drawings, wherein the accompanying drawings are used to supplement the description of the written description so that one can intuitively and intuitively understand each technical feature and overall technical scheme of the present invention, but not to limit the scope of the present invention.
In the description of the present invention, it should be understood that references to orientation descriptions such as upper, lower, front, rear, left, right, etc. are based on the orientation or positional relationship shown in the drawings, are merely for convenience of description of the present invention and to simplify the description, and do not indicate or imply that the apparatus or elements referred to must have a particular orientation, be constructed and operated in a particular orientation, and thus should not be construed as limiting the present invention.
In the description of the present invention, a number means one or more, a number means two or more, and greater than, less than, exceeding, etc. are understood to not include the present number, and above, below, within, etc. are understood to include the present number. The description of the first and second is for the purpose of distinguishing between technical features only and should not be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated or implicitly indicating the precedence of the technical features indicated.
In the description of the present invention, unless explicitly defined otherwise, terms such as arrangement, installation, connection, etc. should be construed broadly and the specific meaning of the terms in the present invention can be reasonably determined by a person skilled in the art in combination with the specific contents of the technical scheme.
Referring to fig. 1 to 10, there is shown a lead-based fast reactor core based on an annular fuel element, including a fuel region 100, a reflection region 200, and a shielding region 300, the reflection region 200 surrounding the fuel region 100, and the shielding region 300 surrounding the reflection region 200. The overall structure of the lead-based fast reactor core based on the annular fuel element is in a short hexagonal prism shape, the diameter of the circumcircle of the core is 626cm, the height of the core is 380cm, and the height of the fuel area 100 is 120cm; the thicknesses of the reflection area 200 and the shielding area 300 at the periphery of the fuel area 100 are 400mm to 460mm, respectively. In this embodiment, the core is a lead-based fast reactor core based on annular fuel elements.
As shown in fig. 1, in order to make the power distribution of the core as flat as possible, the fuel zone 100 includes an inner fuel zone 101 and an outer fuel zone 102 that are separated from each other, and in combination with fig. 2, the fuel zone 100 is provided with a plurality of component positions, gaps between the component positions are cooling channels, the cooling channels are filled with cooling liquid, the cooling liquid is liquid metal lead bismuth, and the liquid metal lead bismuth has a higher heat transfer coefficient than water, so that the heat transfer capability and safety of the core can be significantly improved.
A fuel assembly 110 is positioned in a partial assembly position, an adjustment assembly 120 is positioned in a partial assembly position, and a safety assembly 130 is positioned in a partial assembly position. In this embodiment, 217 component positions are provided for the inner fuel section 101 and 180 component positions are provided for the outer fuel section 102.
Wherein the fuel inner zone 101 has 10 component positions for placing the conditioning component 120 or the safety component 130; the outer fuel zone 102 has 28 component positions for placement of the adjustment component 120 or the safety component 130, and the remaining component positions for placement of the fuel component 110. The adjusting component 120 is used for adjusting the critical, and the safety component 130 can cope with the emergency shutdown and the refueling situation, so as to ensure the safety of the reactor core.
As shown in fig. 1, the positions of the components are arranged layer by layer from the center of the inner fuel area 101 to the outer ring of the outer fuel area 102, and are arranged in a honeycomb shape, the adjusting components 120 are dispersed at the junction of the inner fuel area 101 and the outer fuel area 102 and at the middle position of the inner fuel area 101, and the safety components 130 are uniformly dispersed in the area of the inner fuel area 100. Specifically, the fuel inner zone 101 is provided with 207 fuel assemblies 110, 4 conditioning assemblies 120, 6 safety assemblies 130; the outer fuel zone 102 is provided with 152 fuel assemblies 110, 14 conditioning assemblies 120, 14 safety assemblies 130.
Referring to fig. 2, the fuel assembly 110 has a hexagonal prism shape and a regular hexagonal cross section. The fuel assemblies are not in close contact, the gap between the fuel assemblies is 4.6mm, and the opposite edge distance of the fuel assemblies is 197mm-198mm. The fuel assemblies 110 include a plurality of fuel elements 112, and in this embodiment 169 fuel elements 112 are provided per fuel assembly 110.
As shown in fig. 3 and 4, in particular, the fuel element 112 includes a fuel pellet 1122 and a fuel pellet jacket 1121 surrounding the fuel pellet 1122, and the fuel element 112 has a circular cross section so that both the inner and outer sides of the fuel pellet 1122 can take heat away by the coolant. The fuel assembly 110 includes a fuel housing 111, fuel elements 112 being provided in the fuel housing 111, and a first flow passage 113 through which a cooling liquid flows being provided between each fuel element 112 in the fuel housing 111. It will be appreciated that the fuel element 112 is generally cylindrical in shape and has both inner and outer peripheral surfaces in contact with the coolant to enhance heat dissipation.
The fuel pellets 1122 are MOX fuel, wherein 93% uo2+7% puo2 is used in the inner fuel region 101 and 88.3% uo2+11.7% puo2 is used in the outer fuel region 102. By adopting MOX fuel partition arrangement, the enrichment degree of U235 in and out of the fuel is the same, but the ratio of UO2 to PuO2 is different, the ratio of PuO2 in and out of the fuel to MOX fuel is 7% and 11.7%, which not only can fully utilize fissionable nuclide U238 to realize fuel proliferation, but also is beneficial to flattening of power in the reactor, namely, different enrichment degrees of the fuel are beneficial to flattening of power distribution of the reactor core, so that the material changing cost of the reactor core can be further reduced, and the service life of the reactor core can be prolonged.
The tuning assembly 120 is used to tune the reactivity of the lead-based fast reactor core based on annular fuel elements so that the core is critical at steady state operation. The adjustment assembly 120 is movable up and down in the assembly position. Referring to fig. 5 to 7, specifically, the adjusting assembly 120 has a cylindrical shape, and the adjusting assembly 120 includes first guide pipes 121 and a plurality of adjusting elements 122 disposed in the first guide pipes 121, and in this embodiment, 31 adjusting elements 122 are uniformly distributed in each of the first guide pipes 121. A second flow passage 123 through which the cooling liquid flows is provided between the respective adjustment elements 122 in the adjustment assembly 120.
The safety assembly 130 is used for implementing shutdown operation, the safety assembly 130 can move up and down at the assembly position, and the space left by the single safety assembly after moving is filled with coolant. Referring to fig. 8 to 10, in particular, the safety assembly 130 has a cylindrical shape, and the safety assembly 130 includes second guide pipes 131 and a plurality of safety elements 132 disposed in the second guide pipes 131, and 21 safety elements 132 are uniformly distributed in each second guide pipe 131. A third flow passage 133 for circulating a cooling liquid is provided between the safety elements 132 in the safety module 130.
In order to ensure the safety of the reactor core and reduce the possibility of rod clamping accidents of the reactor core, the embodiment adopts two sets of control systems, namely an adjusting assembly and a safety assembly. The adjusting component is used for adjusting the reactor core reactivity, so that the reactor core is critical in steady-state operation, the safety component is used for coping with emergency shutdown, refueling and other conditions, and the two sets of control systems can independently mediate the reactor to ensure that the reactor is safe in operation or in failure.
The first guide tube 121 may enable the adjustment assembly 120 to be inserted and removed in the assembly position, and the second guide tube 131 may enable the safety assembly 130 to be inserted and removed in the assembly position. As will be appreciated in connection with fig. 1 and 5, during normal service of the core, the safety assemblies 120 are pulled out, the gaps are filled with coolant lead bismuth, and when an emergency accident occurs or shutdown refueling is required, the safety assemblies 120 can be quickly inserted into the core to realize shutdown operation. Referring to fig. 1 and 8, and as will be appreciated in conjunction with fig. 5, the principle of the adjustment assembly 130 and the safety assembly 120 are identical, and can be independently moved up and down along guide slots at the assembly locations to effect core reactivity adjustment.
As shown in FIG. 1, the tuning assemblies 120 are arranged as far as possible at the interface of the inner and outer fuel sections 101, 102 and in the middle of the inner fuel section 101 to avoid over-high power peak factors in the middle of the core and to mitigate the power instability of the core caused by the variation of the enrichment at the division of the inner and outer fuel sections. The fuel assemblies 110 are each provided with a non-fuel section at both ends to connect each other in a compact arrangement.
Referring to fig. 3 and 4, in the fuel element 112, a first air cavity 1123 is provided between the fuel pellet 1122 and the fuel core cladding 1121, and a first air cavity section 1124, a first reflection section 1125 and a first shielding section 1126 are sequentially provided at the upper and lower ends of the fuel pellet 1122.
Referring to fig. 6 and 7, the adjusting element 122 includes an adjusting rod 1222 and an adjusting rod cladding 1221 wrapping the adjusting rod 1222, a second air cavity 1223 is provided between the adjusting rod 1222 and the adjusting rod cladding 1221, the adjusting rod 1222 is made of boron carbide material, and a second reflecting section 1224, a second air cavity section 1225 and a second shielding section 1226 are sequentially provided at an upper end of the adjusting rod 1222.
Referring to fig. 9 and 10, the safety element 132 includes a safety rod 1322 and a safety rod cladding 1321 that wraps the safety rod 1322, a third air cavity 1323 is provided between the safety rod 1322 and the safety rod cladding 1321, the safety rod 1322 is made of a boron carbide material, two ends of the safety rod 1322 are respectively provided with a load material 1324, and the load material 1324 is made of tungsten, so that the safety assembly 130 is not affected by buoyancy caused by coolant when being inserted into the assembly position of the reactor core.
The adjusting rod 1222 is made of boron carbide material, the safety rod 1322 is made of boron carbide material, namely the adjusting component and the absorber of the safety component are made of boron carbide material, wherein the abundance of 10-B10 is 92%, so that the neutron leakage rate is effectively reduced, and the purpose of continuous combustion of the reactor core for a long time is achieved.
In some of these embodiments, the materials of the core cladding 1121, the tuning rod cladding 1221, and the safety rod cladding 1321 are selected from T91 stainless steel, as are the cladding structures to which the reflector assembly and the shielding assembly are applied, and in addition, the first and second reflector segments 1125, 1224 are also selected from T91 stainless steel. To slow down the corrosiveness of the liquid lead bismuth to the cladding, corrosion resistant coatings are added to the surfaces of the core cladding 1121, the modifier rod cladding 1221, and the safety rod cladding 1321. The first shield segments 1126 on the fuel pellets 1122 are all made of boron carbide, the shield material of the shield area 300 is also made of boron carbide, and the second shield segments 1226 on the tuning rod 1222 are made of lead bismuth.
In addition, the shielding region 300 includes a plurality of shielding members, which are identical in structure to the fuel assembly, and only change the material in the fuel assembly to boron carbide.
The thermal power of the lead-based fast reactor core based on the annular fuel element is 300MW, and the refueling period is up to more than 30 full power years. The characteristics are excellent safety performance, long service life and high economical efficiency. The design greatly saves the material changing cost while improving the fuel utilization rate. The application is based on the design thought of the lead-based fast neutron reactor with the ultra-long service life of the annular fuel element, not only can be used as a nuclear power station and for supplying heat and power for a long time in various fields, but also can be used as a research pile for carrying out analysis and research works such as the performance of the related fast neutron breeder, and provides reference value for optimizing the structure of the follow-up fast neutron breeder.
The embodiments of the present invention have been described in detail with reference to the accompanying drawings, but the present invention is not limited to the above embodiments, and various changes can be made within the knowledge of one of ordinary skill in the art without departing from the spirit of the present invention.
Claims (10)
1. A lead-based fast reactor core based on annular fuel elements, characterized by: the fuel cell comprises a fuel area, a reflecting area and a shielding area, wherein the reflecting area is surrounded by the fuel area, and the shielding area is surrounded by the reflecting area; wherein,
The fuel zone comprises a fuel inner zone and a fuel outer zone which are internally and externally divided, the fuel zone is provided with a plurality of component positions, gaps among the component positions are cooling channels, the cooling channels are filled with cooling liquid, and the cooling liquid adopts liquid metal lead bismuth;
A fuel assembly is arranged at part of the assembly position, the fuel assembly comprises a plurality of fuel elements, the fuel elements comprise fuel pellets and a fuel core cladding which wraps the fuel pellets, the section of the fuel elements is annular, so that both the inner side and the outer side of the fuel pellets can take away heat through the coolant;
an adjusting assembly is arranged at part of the assembly positions and used for adjusting the reactivity of the lead-based fast reactor core based on the annular fuel element so that the lead-based fast reactor core based on the annular fuel element is critical in steady-state operation, and the adjusting assembly can move up and down at the assembly positions;
And part of the assembly positions are provided with safety assemblies for implementing shutdown operation, the safety assemblies can move up and down at the assembly positions, and the space left by the single safety assemblies after moving is filled with coolant.
2. The annular fuel element based lead-based fast reactor core of claim 1, wherein: each assembly position is arranged layer by layer from the center of the fuel inner area to the outer ring of the fuel outer area and is in honeycomb arrangement, the adjusting assemblies are dispersed at the junction of the fuel inner area and the fuel outer area and at the middle position of the fuel inner area, and the safety assemblies are uniformly dispersed in the area of the fuel area.
3. The annular fuel element based lead-based fast reactor core of claim 2, wherein: the fuel assembly is in a hexagonal prism shape, the fuel assembly comprises a fuel shell, the fuel elements are arranged in the fuel shell, and a first flow passage for the cooling liquid to circulate is arranged between the fuel elements in the fuel shell.
4. The annular fuel element based lead-based fast reactor core of claim 3, wherein: in the fuel element, a first air cavity is arranged between the fuel pellet and the fuel core cladding, and a first air cavity section, a first reflecting section and a first shielding section are sequentially arranged at the upper end and the lower end of the fuel pellet.
5. The annular fuel element based lead-based fast reactor core of claim 3, wherein: the fuel pellets were MOX fuel, wherein 93% uo2+7% puo2 was used in the inner fuel zone and 88.3% uo2+11.7% puo2 was used in the outer fuel zone.
6. The annular fuel element based lead-based fast reactor core of claim 2, wherein: the adjusting assembly is cylindrical, the adjusting assembly comprises a first guide pipe and a plurality of adjusting elements arranged in the first guide pipe, and a second flow passage for the cooling liquid to circulate is arranged between each adjusting element in the adjusting assembly.
7. The annular fuel element based lead-based fast reactor core of claim 6, wherein: the adjusting element comprises an adjusting rod and an adjusting rod cladding which wraps the adjusting rod, a second air cavity is formed between the adjusting rod and the adjusting rod cladding, the adjusting rod is made of boron carbide, and a second reflecting section, a second air cavity section and a second shielding section are sequentially arranged at the upper end of the adjusting rod.
8. The annular fuel element based lead-based fast reactor core of claim 2, wherein: the safety assembly is cylindrical, the safety assembly comprises a second guide pipe and a plurality of safety elements arranged in the second guide pipe, and a third flow passage for the cooling liquid to circulate is arranged between the safety elements in the safety assembly.
9. The annular fuel element based lead-based fast reactor core of claim 8, wherein: the safety element comprises a safety rod and a safety rod cladding which wraps the safety rod, a third air cavity is arranged between the safety rod and the safety rod cladding, the safety rod is made of boron carbide material, and load materials are respectively arranged at two ends of the safety rod.
10. The annular fuel element based lead-based fast reactor core of any one of claims 2 to 9, wherein: the fuel inner zone is provided with 217 component positions, the fuel inner zone is provided with 10 component positions for placing the adjusting component or the safety component, the fuel outer zone is provided with 180 component positions, and the fuel outer zone is provided with 28 component positions for placing the adjusting component or the safety component.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311874075.8A CN117976255A (en) | 2023-12-29 | 2023-12-29 | Lead-based fast reactor core based on annular fuel element |
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| Application Number | Priority Date | Filing Date | Title |
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| CN202311874075.8A CN117976255A (en) | 2023-12-29 | 2023-12-29 | Lead-based fast reactor core based on annular fuel element |
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| CN117976255A true CN117976255A (en) | 2024-05-03 |
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| CN202311874075.8A Pending CN117976255A (en) | 2023-12-29 | 2023-12-29 | Lead-based fast reactor core based on annular fuel element |
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