CN116598026A - High-temperature fuel element of solid reactor core - Google Patents
High-temperature fuel element of solid reactor core Download PDFInfo
- Publication number
- CN116598026A CN116598026A CN202310567940.8A CN202310567940A CN116598026A CN 116598026 A CN116598026 A CN 116598026A CN 202310567940 A CN202310567940 A CN 202310567940A CN 116598026 A CN116598026 A CN 116598026A
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- China
- Prior art keywords
- cladding
- fuel element
- temperature fuel
- high temperature
- solid core
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 239000000446 fuel Substances 0.000 title claims abstract description 52
- 239000007787 solid Substances 0.000 title claims abstract description 37
- 238000005253 cladding Methods 0.000 claims abstract description 79
- 239000008188 pellet Substances 0.000 claims abstract description 22
- 238000011049 filling Methods 0.000 claims abstract description 5
- 238000005192 partition Methods 0.000 claims description 6
- 238000009423 ventilation Methods 0.000 claims 1
- 238000012546 transfer Methods 0.000 abstract description 15
- 238000013461 design Methods 0.000 abstract description 12
- 239000011159 matrix material Substances 0.000 abstract description 12
- 239000000463 material Substances 0.000 abstract description 8
- 238000003466 welding Methods 0.000 description 5
- 238000012545 processing Methods 0.000 description 4
- 229910052770 Uranium Inorganic materials 0.000 description 3
- 239000000306 component Substances 0.000 description 3
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 3
- 238000002485 combustion reaction Methods 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 238000003780 insertion Methods 0.000 description 2
- 230000037431 insertion Effects 0.000 description 2
- 238000009434 installation Methods 0.000 description 2
- 230000008961 swelling Effects 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 229910000711 U alloy Inorganic materials 0.000 description 1
- 230000004323 axial length Effects 0.000 description 1
- MVXWAZXVYXTENN-UHFFFAOYSA-N azanylidyneuranium Chemical compound [U]#N MVXWAZXVYXTENN-UHFFFAOYSA-N 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 239000011248 coating agent Substances 0.000 description 1
- 238000000576 coating method Methods 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 239000008358 core component Substances 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000001125 extrusion Methods 0.000 description 1
- 238000002955 isolation Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- OOAWCECZEHPMBX-UHFFFAOYSA-N oxygen(2-);uranium(4+) Chemical compound [O-2].[O-2].[U+4] OOAWCECZEHPMBX-UHFFFAOYSA-N 0.000 description 1
- 239000011148 porous material Substances 0.000 description 1
- 238000003825 pressing Methods 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 238000005096 rolling process Methods 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 229910021332 silicide Inorganic materials 0.000 description 1
- FVBUAEGBCNSCDD-UHFFFAOYSA-N silicide(4-) Chemical compound [Si-4] FVBUAEGBCNSCDD-UHFFFAOYSA-N 0.000 description 1
- 125000006850 spacer group Chemical group 0.000 description 1
- FCTBKIHDJGHPPO-UHFFFAOYSA-N uranium dioxide Inorganic materials O=[U]=O FCTBKIHDJGHPPO-UHFFFAOYSA-N 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
- G21C3/08—Casings; Jackets provided with external means to promote heat-transfer, e.g. fins, baffles
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
The invention provides a solid core high temperature fuel element, comprising: the inner cladding is used for filling annular pellets in a space formed between the outer cladding and the inner cladding, and a vent hole is formed in one end face of the inner cladding, connected with the outer cladding; the inner cladding forms a hollow duct inside, and a heat removal device is inserted into the hollow duct. Through the element design of double cladding, the problem of the matching of the solid reactor core heat pipe plug-in heat exchange and the fuel element structure is solved, and the core block material with high heat conductivity is matched and selected, so that the additional matrix material is not required, and the heat transfer path is reduced.
Description
Technical Field
The invention belongs to the technical field of fuel elements for nuclear power devices, and particularly relates to a solid reactor core high-temperature fuel element.
Background
The statements in this section merely provide background information related to the present disclosure and may not necessarily constitute prior art.
The pressurized water nuclear reactor fuel assembly is generally composed of a plurality of fuel rods, guide tube members, instrumentation tube members, grids, upper and lower tube seats, etc., and can be classified into 14x14 to 20x20 square and hexagonal types, etc., according to the arrangement of the fuel rods. The fuel rod is cylindrical in shape and consists of uranium dioxide pellets, a cladding, upper and lower end plugs and air cavity springs. The fuel assembly accomplishes the heat transfer by cooling water. The solid reactor core nuclear power device adopts a heat transfer medium different from a pressurized water reactor, and heat released by fuel is transferred in the modes of solid heat conduction, gap contact heat conduction, heat radiation, air gap heat conduction and the like. The advantage of high operating temperatures being a solid core is also a design difficulty. Theoretically, the operating temperature of the solid core is not limited by the boiling point and flow state of the working medium, and thus can withstand higher operating temperatures. But in engineering, gaps between solid core components have a great influence on heat transfer, and release of fission products can further exacerbate component deformation, affecting heat transfer. The solid core needs to provide space for heat removal devices (e.g., heat pipes, etc.) further adding to the complexity and difficulty of structural design.
The common solid reactor core adopts a matrix without fissionable nuclides, circular holes are processed in the matrix, rod-shaped fuel elements are inserted into the holes, and a heat pipe is arranged in the other part of the holes. In the solid reactor core in the form, 5 heat transfer links are adopted from a heat source to a cold source, namely, a pellet-cladding gap, a cladding-matrix gap, a matrix material and a matrix-heat pipe gap, wherein the heat transfer path is complex, the temperature difference is large, and the running temperature of the solid reactor core is limited; the matrix is difficult to process, and particularly, a large-length reactor core is difficult to realize, the reactor core power is difficult to expand, and the length of the axial air cavity and the length of the reflecting layer of the fuel element are limited.
Disclosure of Invention
In order to solve the problems, the invention provides a solid core high-temperature fuel element, which solves the problem of matching the solid core heat pipe plug-in heat exchange with the fuel element structure through the element design of double cladding, and is matched with a core block material with high heat conductivity, so that no additional matrix material is required, and the heat transfer path is shortened.
According to some embodiments, the present invention employs the following technical solutions: a solid core high temperature fuel element comprising: the inner cladding is used for filling annular pellets in a space formed between the outer cladding and the inner cladding, and a vent hole is formed in one end face of the inner cladding, connected with the outer cladding; the inner cladding forms a hollow duct inside, and a heat removal device is inserted into the hollow duct.
In addition, a solid core high temperature fuel element according to an embodiment of the present invention may also have the following additional technical features:
preferably, the inner cladding is in sealing connection with one end of the outer cladding through an upper end plug, the inner cladding is connected with the other end of the outer cladding through a lower supporting partition plate, and a plurality of vent holes are formed in positions, opposite to a space formed between the lower supporting partition plate and the outer cladding and the inner cladding.
Preferably, the end of the outer envelope is sealingly connected to a lower end plug, the lower end plug, outer envelope and lower support bulkhead forming an air cavity.
Preferably, the outer envelope may be one of hexagonal, triangular, square.
Preferably, the upper end plug is of hollow structure.
Preferably, an air chamber is connected to one end of the vent hole in the axial extension direction of the outer envelope.
Preferably, reflective layer pellets are provided in the space formed between the outer and inner cladding, the reflective layer pellets being provided at both ends of the annular pellets.
Preferably, a positioning spring is arranged in a space formed between the outer cladding and the inner cladding, one end of the positioning spring is in contact with the reflecting layer core block, and the outer diameter of the positioning spring is larger than the inner diameter of the outer cladding.
Preferably, the heat removal device is a heat pipe.
Preferably, the other end of the positioning spring is not in contact with the upper end plug.
The one or more of the above technical solutions have the following beneficial effects:
in the invention, through the element design of double cladding, the problem of the plug-in heat exchange of the solid reactor core heat pipe and the matching of the fuel element structure is solved. The solid reactor core adopts a mode of direct heat conduction of the matrix to transfer heat released by the fuel elements, and no heat pipe exists between the fuel elements. The arrangement of the heat pipes can only be achieved by arranging mounting channels in the middle of the elements. The double-cladding fuel element structure forms a passage for inserting a heat pipe through the design of annular fuel and matching with the inner cladding. The annular fuel is made of a core block material with high heat conductivity, so that no additional matrix material is needed, and the heat transfer path is shortened.
According to the invention, through the design of the double cladding, the swelling deformation of the pellet is carried out in two directions, the stress of a single cladding is reduced, the safety margin is higher, and the problems of damage of the cladding of the fuel element and the leakage of radioactive substances caused by a PC I mechanism are solved. The traditional fuel element is formed by matching the solid core block and the outer cladding with the end plug, and coating the solid core block is completed. Swelling deformation of the core during service can only progress outwards, and the outer envelope bears all the forces exerted by the core. The double cladding is matched with the design of the annular pellet, so that the unilateral expansion amount of the pellet is reduced, the force applied to the unilateral cladding is further reduced, the PC I effect is relieved, and the safety margin is increased.
Additional aspects of the invention will be set forth in part in the description which follows and, in part, will be obvious from the description, or may be learned by practice of the invention.
Drawings
The accompanying drawings, which are included to provide a further understanding of the invention and are incorporated in and constitute a part of this specification, illustrate embodiments of the invention and together with the description serve to explain the invention.
FIG. 1 is a schematic view of a combustion element according to a first embodiment of the present invention;
fig. 2 is a schematic view of the structure of a lower support plate according to an embodiment of the present invention.
In the figure, 1, an upper end plug, 2, a positioning spring, 3, a reflecting layer core block, 4, an annular core block, 5, an inner cladding, 6, a lower supporting baffle plate, 7, an outer cladding, 8, a lower end plug, 9 and a vent hole
Detailed Description
It should be noted that the following detailed description is illustrative and is intended to provide further explanation of the invention. Unless defined otherwise, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this invention belongs.
In the present invention, terms such as "upper", "lower", "left", "right", "front", "rear", "vertical", "horizontal", "side", "bottom", etc. refer to an orientation or a positional relationship based on that shown in the drawings, and are merely relational terms, which are used for convenience in describing structural relationships of various components or elements of the present invention, and do not denote any one of the components or elements of the present invention, and are not to be construed as limiting the present invention. In the present invention, terms such as "fixedly attached," "connected," "coupled," and the like are to be construed broadly and refer to either a fixed connection or an integral or removable connection; can be directly connected or indirectly connected through an intermediate medium. The specific meaning of the terms in the present invention can be determined according to circumstances by a person skilled in the relevant art or the art, and is not to be construed as limiting the present invention.
Example 1
As shown in fig. 1-2, the present embodiment discloses a solid core high temperature fuel element, which is characterized by comprising: an outer cladding 7 and an inner cladding 5, wherein a space formed between the outer cladding 7 and the inner cladding 5 is used for filling the annular core block 4, and a vent hole 9 is formed on one end surface of the inner cladding 5 connected with the outer cladding 7; the inner cladding 5 is internally formed with a hollow duct in which a heat removal device is inserted.
In this embodiment, through the design of two cladding, the fuel element is hollow columnar structure, inserts the heat remove device in the cavity pore of inner cladding, and annular pellet 4 sets up between outer cladding 7 and inner cladding 5, has solved the problem that solid core heat pipe insert heat transfer and fuel element structure match, cooperates the pellet material of selecting to have high thermal conductivity, no longer need additionally set up the matrix material, has reduced the heat transfer path.
In this embodiment, the annular core 4 is made of uranium nitride, uranium silicide, uranium carbide, metallic uranium, an alloy of uranium, or a mixture of one or more of them.
Specifically, one end of the inner casing 5 is connected to the upper end plug 1 by welding, the other end of the inner casing 5 is connected to the lower support partition 6 by welding or the like, one end of the outer casing 7 is connected to the upper end plug 1 by welding or the like, and the other end of the outer casing 7 is connected to the lower end plug 8 by welding or the like. The outer envelope 7, the lower support partition 6 and the lower end plug 8 form an air cavity.
The annular pellet 4 is encapsulated between the outer cladding 7 and the inner cladding 5 through the upper end plug 1 and the lower support baffle 6, and a plurality of vent holes 9 are formed in the upper and lower support baffle 6 in the axial direction of the annular pellet 4, so that the fission gas of the annular pellet enters the air cavity through the vent holes 9.
The welded structure of the lower support spacer 6 and the inner cladding 5 provides physical isolation of the heat removal device from the pellets.
Alternatively, the heat removal device employs a heat pipe inserted into a hollow bore in the combustion element to absorb heat and transfer the heat to a heat exchanger at the other end, wherein the heat exchanger is disposed at the end of the heat pipe extending out of the fuel element, i.e., the upper end plug end.
In this embodiment, the inner and outer cladding of the fuel element can be manufactured by pipe production processes such as extrusion, rolling, drawing, etc., without length limitation, and the difficulty in processing the elongated through hole of the base material is solved. The common solid reactor core adopts a matrix without fissionable nuclide, a circular hole is processed in the matrix, a rod-shaped fuel element is inserted into the hole, a heat pipe is filled into the other part of the holes, the deep hole processing has large aperture ratio, the size and form and position tolerance of the hole are difficult to ensure, and then the insertion of the fuel rod and the heat pipe is influenced, and the performance and the safety of the reactor core are influenced. The structure of the double-layer cladding directly provides an installation channel for the heat pipe through the inner wall of the inner cladding, so that deep holes do not need to be processed on a base material, and the difficulty in processing the slender through holes of the base material is solved; and because the pipe processing has no length limitation, the axial reflecting layer and the air cavity can be conveniently arranged, flexible axial space is provided for the reactor core design, and a foundation is provided for a solid reactor core with larger size and larger power.
In this embodiment, in order to prevent the active region from moving during transportation and operation, a positioning spring 2 is disposed in a space formed between the outer casing 7 and the inner casing 5, one end of the positioning spring 2 is in contact with the end of the reflecting layer pellet, the other end is not in contact with the upper end plug, the outer diameter of the positioning spring is slightly larger than the inner diameter of the outer casing, and the pressing of the positioning spring on the inner wall of the outer casing and the limiting of the pellet are realized through interference fit. The positioning spring 2 fixes the position of the active area on the one hand, space is provided for the irradiation growth of the core block on the other hand, the length of the positioning spring 2 is smaller than the axial length from the top of the core block of the reflecting layer to the upper end plug, and the thrust caused by the irradiation growth of the core block can enable the positioning spring 2 to move along the pipe wall.
It will be appreciated that the inner envelope 5 is located within the inner hollow region of the positioning spring 2.
In this embodiment, the space formed between the outer cladding 7 and the inner cladding 5 is provided with the reflective layer core blocks 3, the two ends of the active region, namely the annular core blocks 4, are provided with the axial reflective layers, each axial reflective layer is composed of a plurality of reflective layer core blocks 3, the axial reflective layers are closely arranged with the upper and lower end core blocks of the active region, and the lengths of the reflective layers are designed according to the requirements of different reactor cores. The axial reflecting layer can improve neutron economy, reduce the number of core elements and achieve the purpose of a compact core.
In this embodiment, the outer casing 7 is designed into a different deformation section, such as a hexagon, a triangle, a positive direction, etc., according to the function requirement, and the outer surface structure can be modified and adjusted according to different use environments, so as to enhance the applicability to the environment.
In this embodiment, with the independent fuel element as the basic heat transfer unit, the fuel element can be designed into a shape with capacity of fully distributing space, such as a hexagon, a triangle, a square, etc., and the alignment arrangement of the polygon sides and the inherent stable structure, i.e. the polygon sides, are used as the supporting surface, so that the transverse arrangement of the fuel element is more stable than the transverse arrangement of the rod-shaped structure, and the compact topological arrangement of the fuel element can be realized, thereby realizing the self-filling, self-positioning and self-limiting of the fuel element.
Alternatively, the shape of the vent holes in the lower support baffle 6 may be designed as desired.
As an alternative mode, the air cavity can be independently designed, and is connected with the outer casing by adopting a welding mode and the like, so that the air cavity structure with different designs is realized, the structure application range is enlarged, and the purposes of high fuel consumption of the fuel element and no material replacement in the service life of the nuclear reactor are realized.
In this embodiment, the upper end plug 1 is designed as a hollow structure providing an insertion passage for the heat pipe.
The novel fuel element structure form is adopted, so that the problems of heat exchange of the solid reactor core and arrangement of the fuel elements are effectively solved. By the design of the inner cladding and the outer cladding, the purposes of safe and reliable heat transfer of the fuel element and compact installation in the reactor core are realized.
While the foregoing description of the embodiments of the present invention has been presented in conjunction with the drawings, it should be understood that it is not intended to limit the scope of the invention, but rather, it is intended to cover all modifications or variations within the scope of the invention as defined by the claims of the present invention.
Claims (10)
1. A solid core high temperature fuel element comprising: the inner cladding is used for filling annular pellets in a space formed between the outer cladding and the inner cladding, and a vent hole is formed in one end face of the inner cladding, connected with the outer cladding; the inner cladding forms a hollow duct inside, and a heat removal device is inserted into the hollow duct.
2. The solid core high temperature fuel element of claim 1, wherein one end of said inner cladding and said outer cladding are sealingly connected by an upper end plug, the other end of said inner cladding and said outer cladding are connected by a lower support partition, and a plurality of ventilation holes are provided in said lower support partition opposite to the space formed between said outer cladding and said inner cladding.
3. The solid core high temperature fuel element of claim 2, wherein the end of the outer cladding is sealingly connected to a lower end plug, the lower end plug, outer cladding and lower support bulkhead forming an air cavity.
4. The solid core high temperature fuel element of claim 1, wherein said outer cladding is one of hexagonal, triangular, square.
5. The solid core high temperature fuel element of claim 2, wherein said upper end plug is hollow.
6. The solid core high temperature fuel element of claim 1, wherein an air chamber is connected at one end of the vent hole in the axial extension of the outer cladding.
7. The solid core high temperature fuel element as claimed in claim 1, wherein reflective layer pellets are disposed in a space formed between the outer cladding and the inner cladding, the reflective layer pellets being disposed at both ends of the annular pellets.
8. The solid core high temperature fuel element of claim 1, wherein a positioning spring is disposed in a space formed between the outer cladding and the inner cladding, one end of the positioning spring being in contact with the reflective layer pellet, an outer diameter of the positioning spring being greater than an inner diameter of the outer cladding.
9. The solid core high temperature fuel element of claim 1, wherein said heat removal means is a heat pipe.
10. The solid core high temperature fuel element of claim 8, wherein the other end of said positioning spring is not in contact with the upper end plug.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310567940.8A CN116598026A (en) | 2023-05-18 | 2023-05-18 | High-temperature fuel element of solid reactor core |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310567940.8A CN116598026A (en) | 2023-05-18 | 2023-05-18 | High-temperature fuel element of solid reactor core |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN116598026A true CN116598026A (en) | 2023-08-15 |
Family
ID=87598697
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202310567940.8A Pending CN116598026A (en) | 2023-05-18 | 2023-05-18 | High-temperature fuel element of solid reactor core |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN116598026A (en) |
-
2023
- 2023-05-18 CN CN202310567940.8A patent/CN116598026A/en active Pending
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