CN113793701A - Spiral cross-shaped metal fuel element reactor core - Google Patents
Spiral cross-shaped metal fuel element reactor core Download PDFInfo
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- CN113793701A CN113793701A CN202110978390.XA CN202110978390A CN113793701A CN 113793701 A CN113793701 A CN 113793701A CN 202110978390 A CN202110978390 A CN 202110978390A CN 113793701 A CN113793701 A CN 113793701A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/34—Spacer grids
- G21C3/3424—Fabrication of spacer grids
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/324—Coats or envelopes for the bundles
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/336—Spacer elements for fuel rods in the bundle
- G21C3/338—Helicoidal spacer elements
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- 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
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/60—Metallic fuel; Intermetallic dispersions
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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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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Dispersion Chemistry (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a spiral cross-shaped metal fuel element reactor core, which comprises a reactor core active region, a radial reflecting layer, an axial upper reflecting layer and an axial lower reflecting layer; the reflecting layer is made of aluminum oxide; the core active area comprises a first area assembly, a second area assembly and a control rod assembly; the three types of components are densely paved by 6 circles of regular hexagons; the fuel elements are in a spiral cross shape and are arranged in a triangular shape, the fuel is U-Zr alloy with the Zr content of 10% by mass, the U235 enrichment degree is 19.75%, and the cladding material is stainless steel; the control rod assembly comprises a control body, a guide cylinder and an assembly box; the control body comprises a cylindrical boron carbide control rod and a stainless steel ladle shell; the invention effectively reduces the reactor core volume and has lower fuel peak temperature while maintaining the excellent thermal hydraulic performance of the spiral fuel, and is suitable for a novel reactor which is miniaturized, has high temperature parameters and gives consideration to the economical efficiency.
Description
Technical Field
The invention belongs to the technical field of advanced nuclear energy development, and particularly relates to a spiral cross-shaped metal fuel element reactor core.
Background
As a high-performance novel fuel, the spiral fuel has better thermal hydraulic performance, and can improve the power density of the reactor core under the same safety limit value, so that the outlet temperature of the reactor core is improved, the thermal efficiency of an energy conversion system is improved, and the economy of the reactor is facilitated. The existing scheme is generally in spiral cross fuel-quadrilateral arrangement and spiral triangular fuel-triangular arrangement, the adopted fuel is ceramic fuel pellet or TRISO type fuel, the thermal conductivity is relatively low, the peak temperature of the fuel is high, and the advantage of spiral fuel is not favorably utilized; meanwhile, due to the limitation of enrichment degree, the TRISO fuel often causes larger core volume in order to achieve higher fuel consumption.
Disclosure of Invention
In accordance with the limitations of the prior art, the present invention is directed to a spiral cross-shaped metal fuel element core having better heat exchange capability and lower peak fuel temperature while reducing the core volume.
In order to achieve the purpose, the invention adopts the following technical scheme:
the spiral cross-shaped metal fuel element reactor core comprises a reactor core active region 1, a radial reflecting layer 2, an axial upper reflecting layer 3 and an axial lower reflecting layer 4;
the core active area 1 of the spiral cross-shaped metal fuel element core comprises a first area assembly 1-1-A, a second area assembly 1-1-B and a control rod assembly 1-2; the three types of assemblies are densely paved by 6 circles of regular hexagons, and no assembly is arranged at the hexagonal position of the outermost circle, so that the reactor core active area 1 has 121 box assemblies in total; three circles in the center of the core active area 1 are first area components 1-1-A, the rest are second area components 1-1-B, 7 groups of first area components 1-1-A are replaced by control rod components 1-2 at the center position and the hexagonal position of the third circle, 6 groups of second area components 1-1-B are replaced at the middle edge position of the fifth circle, so that 13 groups of control rod components 1-2, 37 groups of first area components 1-1-A (including 7 groups of control rod components), and 84 groups of second area components 1-1-B (including 6 groups of control rod components) are provided;
the spiral cross-shaped metal fuel element core, the first zone assembly 1-1-A and the second zone assembly 1-1-B respectively comprise fuel elements 1-1-1, coolant channels 1-1-2 and assembly boxes 1-1-3 covering the fuel elements 1-1-1 and the coolant channels 1-1-2; the fuel elements 1-1-1 adopt a spiral cross shape, the fuel grid elements are arranged in a triangular shape, 6 circles are uniformly distributed in the first zone assembly 1-1-A and the second zone assembly 1-1-B, and the adjacent fuel elements 1-1-1 can be in point contact at petal positions after being twisted for 30 degrees, so that compared with the existing spiral cross-shaped fuel elements arranged in a quadrilateral shape, the fuel elements have more fixed points; the region between the fuel elements 1-1-1 is a coolant passage 1-1-2; the fuel of the fuel element 1-1-1 is a U-Zr alloy with 10% of Zr mass content and 19.75% of U235 enrichment degree.
The cladding materials of the fuel element 1-1-1 and the component box 1-1-3 are stainless steel.
In the spiral cross-shaped metal fuel element reactor core, a reactor core active region 1 is embedded in a radial reflecting layer 2, the reactor core active region and the radial reflecting layer are equal in height, and the upper end surface, the lower end surface and the central axis of the reactor core active region are respectively superposed; the axial upper reflecting layer 3 and the axial lower reflecting layer 4 are respectively connected with the upper end surface and the lower end surface of the reactor core active region 1, the central axis is superposed with the reactor core active region 1, and the diameter of the central axis is equal to that of the radial reflecting layer 2; the radial reflecting layer 2, the axial upper reflecting layer 3 and the axial lower reflecting layer 4 are made of aluminum oxide.
The control rod assembly 1-2 of the spiral cross-shaped metal fuel element reactor core comprises a control body 1-2-1, a guide cylinder 1-2-2 and a control rod assembly box 1-2-3; each control rod assembly 1-2 adopts 2 circles of control bodies 1-2-1 which are arranged in a hexagon, so that 7 control bodies 1-2-1 are arranged and surrounded by a stainless steel material guide cylinder 1-2-2, and each control body 1-2-1 comprises a cylindrical boron carbide control rod and a stainless steel ladle shell for coating the cylindrical boron carbide control rod; the control rod assembly box 1-2-3 coaxially surrounds the guide cylinder 1-2-2; the gaps among the control body 1-2-1, the guide cylinder 1-2-2 and the control rod assembly box 1-2-3 are coolant channels.
Compared with the prior art, the invention has the following advantages:
1. the spiral cross-shaped metal fuel element effectively reduces the reactor core volume and has lower fuel peak temperature while maintaining the excellent thermal hydraulic performance of spiral fuel, and is suitable for a novel reactor which is miniaturized, has high temperature parameters and gives consideration to economy.
2. The spiral cross-shaped metal fuel element adopts U-Zr alloy fuel with the Zr mass content of 10%, and the volume loading capacity is higher than that of the ceramic material or TRISO fuel adopted by the existing spiral fuel; therefore, the invention effectively reduces the volume of the reactor core under the same burning-up requirement.
3. The U-Zr alloy fuel has low heat conductivity, and compared with a rod-shaped original piece, the U-Zr alloy fuel effectively reduces the peak temperature of the pellet under the premise of the same thermal power, so that the reactor power can be improved under the same safety margin, the outlet temperature of the coolant is improved, and the economy of the reactor is facilitated.
4. The spiral cross-shaped metal fuel elements are arranged in a triangular mode, adjacent fuel elements are in point contact at petal positions after being twisted for 30 degrees, supporting and fixing effects are achieved, and existing spiral cross-shaped elements arranged in a square mode are in point contact when being twisted for 90 degrees. Therefore, under the same pitch, the reactor core has better stability in the radial direction and the circumferential direction, and is beneficial to resisting flow-induced vibration.
Drawings
FIG. 1 is a schematic cross-sectional view of a helical cruciform metal fuel element core of the present invention.
FIG. 2 is a longitudinal cross-sectional view of the helical cruciform metal fuel element core of the present invention taken along the direction of FIGS. 1C-C.
FIG. 3 is a schematic view of the primary and secondary assemblies of the helical cruciform metal fuel element core of the present invention.
FIG. 4 is a schematic view of a control rod assembly of the helical cruciform metal fuel element core of the present invention.
In the above drawings: 1: a core active area; 2: a radially reflective layer; 3: an axially upper reflective layer; 4: an axially lower reflective layer; 1-1-A: a zone assembly; 1-1-B: a second zone component; 1-2: a control rod assembly; 1-1-1: a fuel element; 1-1-2: a coolant passage; 1-1-3: a component cartridge; 1-2-1: a control body; 1-2-2: a guide cylinder; 1-2-3: a control rod assembly box.
Detailed Description
The invention provides a spiral cross-shaped metal fuel element core, which is further described in detail by taking a small-sized villiaumite-cooled high-temperature reactor core with the thermal power of the core of 125MW and the coolant of FLiBe as an example in combination with the attached drawing. Referring to fig. 1 and 2, an embodiment of a spiral cross fuel element small fluorine salt cooled high temperature stack of the present invention is shown.
As shown in fig. 2, the spiral cross-shaped metal fuel element core includes a core active region 1, a radial reflector layer 2, an axial upper reflector layer 3, and an axial lower reflector layer 4; in the spiral cross-shaped metal fuel element reactor core, a reactor core active region 1 is embedded in a radial reflecting layer 2, the reactor core active region and the radial reflecting layer are equal in height, and the upper end surface, the lower end surface and the central axis of the reactor core active region are respectively superposed; the axial upper reflecting layer 3 and the axial lower reflecting layer 4 are respectively connected with the upper end surface and the lower end surface of the reactor core active region 1, the central axis is superposed with the reactor core active region 1, and the diameter of the central axis is equal to that of the radial reflecting layer 2; the radial reflecting layer 2, the axial upper reflecting layer 3 and the axial lower reflecting layer 4 are made of aluminum oxide.
As shown in FIG. 1, the helical cross-shaped metal fuel element core, the core active area 1 includes a primary assembly 1-1-A, a secondary assembly 1-1-B and a control rod assembly 1-2; the three types of assemblies are densely paved by 6 circles of regular hexagons, and no assembly is arranged at the hexagonal position of the outermost circle, so that the reactor core active area 1 has 121 box assemblies in total; three circles in the center of the core active area 1 are first area components 1-1-A, the rest are second area components 1-1-B, 7 groups of first area components 1-1-A are replaced by control rod components 1-2 at the center position and the hexagonal position of the third circle, 6 groups of second area components 1-1-B are replaced by control rod components 1-2 at the middle edge position of the fifth circle, so that 13 groups of control rod components 1-2 are shared, 37 groups of first area components 1-1-A are shared (including 7 groups of control rod components), and 84 groups of second area components 1-1-B are shared (including 6 groups of control rod components).
As shown in fig. 3, the spiral cross-shaped metal fuel element core, the first zone assembly 1-1-a and the second zone assembly 1-1-B each include a fuel element 1-1-1, a coolant channel 1-1-2, and an assembly box 1-1-3 covering the fuel element 1-1-1 and the coolant channel 1-1-2; the fuel elements 1-1-1 adopt a spiral cross shape, the fuel grid elements are arranged in a triangular shape, 6 circles are uniformly distributed in the first zone assembly 1-1-A and the second zone assembly 1-1-B, and the adjacent fuel elements 1-1-1 can be in point contact at petal positions after being twisted for 30 degrees, so that compared with the existing spiral cross-shaped fuel elements arranged in a quadrilateral shape, the fuel elements have more fixed points; the region between the fuel elements 1-1-1 is a coolant passage 1-1-2; the fuel of the fuel element 1-1-1 is a U-Zr alloy with 10 percent of Zr mass content, and the enrichment degree of U235 is 19.75 percent; the cladding materials of the fuel element 1-1-1 and the component box 1-1-3 are stainless steel;
as shown in FIG. 4, the spiral cross-shaped metal fuel element core, the control rod assembly 1-2 includes a control body 1-2-1, a guide cylinder 1-2-2 and a control rod assembly box 1-2-3; each control rod assembly 1-2 adopts 2 circles of control bodies 1-2-1 which are arranged in a hexagon, so that 7 control bodies 1-2-1 are arranged and surrounded by a stainless steel material guide cylinder 1-2-2, and each control body 1-2-1 comprises a cylindrical boron carbide control rod and a stainless steel ladle shell for coating the cylindrical boron carbide control rod; the control rod assembly box 1-2-3 coaxially surrounds the guide cylinder 1-2-2; the gaps among the control body 1-2-1, the guide cylinder 1-2-2 and the control rod assembly box 1-2-3 are coolant channels.
Taking the example of cooling the core of the high-temperature reactor by small-sized villiaumite as an example: the thermal power of a reactor core is 125MW, the coolant is FLiBe, the inlet temperature is 650 ℃, the outlet temperature is 700 ℃, the enrichment degree is 19.75 percent, and the fuel consumption requirement is met>104MWd/Tu. Through physical and three-dimensional fine thermal calculation of a three-dimensional transport reactor, the diameter of a reactor core calculated by the scheme of the invention is 228cm, the height of an active region is 80cm, and the thicknesses of an upper reflecting layer and a lower reflecting layer are 20 cm; under the condition of no poison, the range of the radial power factor is (0.758-1.289), the range of the axial power factor is (0.792-1.183), and the peak temperature of the fuel is 1193.63K; the height of the active region obtained by calculation by adopting a volume fraction 50% TRISO scheme is 340 cm; if a rod type fuel element is used, the calculated active zone height is 400cm and the fuel peak temperature is 1383.46K. In conclusion, the reactor core volume is effectively reduced under the same burnup requirement; compared with a bar-shaped original piece, the peak temperature of the core block is effectively reduced, andthereby contributing to the economy of the reactor.
While the invention has been described in further detail with reference to specific preferred embodiments thereof, it will be understood by those skilled in the art that various changes in form and details may be made therein without departing from the spirit and scope of the invention as defined by the appended claims.
Claims (5)
1. The spiral cross-shaped metal fuel element core is characterized in that: the reactor core comprises a reactor core active region (1), a radial reflecting layer (2), an axial upper reflecting layer (3) and an axial lower reflecting layer (4);
the core active area (1) comprises a first area assembly (1-1-A), a second area assembly (1-1-B) and a control rod assembly (1-2); the three types of assemblies are densely paved by 6 circles of regular hexagons, and no assembly is arranged at the hexagonal position of the outermost circle, so that the reactor core active area (1) has 121 box assemblies in common; three circles in the center of the core active area (1) are provided with a first area assembly (1-1-A), the rest are provided with a second area assembly (1-1-B), the central position of the control rod assembly (1-2) and the hexagonal position of the third circle replace 7 groups of the first area assembly (1-1-A), the middle edge position of the fifth circle replaces 6 groups of the second area assembly (1-1-B), so that 13 groups of the control rod assembly (1-2) are provided, the first area assembly (1-1-A) comprises 37 groups of the 7 groups of the control rod assembly, and the second area assembly (1-1-B) comprises 84 groups of the 6 groups of the control rod assembly;
the first-zone assembly (1-1-A) and the second-zone assembly (1-1-B) each comprise a fuel element (1-1-1), a coolant channel (1-1-2), and an assembly box (1-1-3) covering the fuel element (1-1-1) and the coolant channel (1-1-2); the fuel elements (1-1-1) adopt a spiral cross shape, the fuel grid elements are arranged in a triangular shape, 6 circles are uniformly distributed in the first region assembly (1-1-A) and the second region assembly (1-1-B), and the adjacent fuel elements (1-1-1) can be in point contact at the petal position after being twisted for 30 degrees, so that compared with the existing spiral cross-shaped fuel elements arranged in a quadrilateral shape, the fuel elements have more fixed points; the region between the fuel elements (1-1-1) is a coolant passage (1-1-2); the fuel of the fuel element (1-1-1) is a U-Zr alloy with 10% of Zr mass content and 19.75% of U235 enrichment degree.
2. The spiral cross metal fuel element core as claimed in claim 1, wherein: the cladding materials of the fuel element (1-1-1) and the component box (1-1-3) are stainless steel.
3. The spiral cross metal fuel element core as claimed in claim 1, wherein: the reactor core active region (1) is embedded in the radial reflecting layer (2), the reactor core active region and the radial reflecting layer are equal in height, and the upper end surface, the lower end surface and the central axis of the reactor core active region are respectively superposed; the axial upper reflecting layer (3) and the axial lower reflecting layer (4) are respectively connected with the upper end surface and the lower end surface of the reactor core active region (1), the central axis is superposed with the reactor core active region (1), and the diameter of the central axis is equal to that of the radial reflecting layer (2).
4. The spiral cross metal fuel element core as claimed in claim 1, wherein: the radial reflecting layer (2), the axial upper reflecting layer (3) and the axial lower reflecting layer (4) are made of aluminum oxide.
5. The spiral cross metal fuel element core as claimed in claim 1, wherein: the control rod assembly (1-2) comprises a control body (1-2-1), a guide cylinder (1-2-2) and a control rod assembly box (1-2-3); each control rod assembly (1-2) adopts 2 circles of control bodies (1-2-1) which are arranged in a hexagon, so that 7 control bodies (1-2-1) are arranged and are surrounded by a stainless steel material guide cylinder (1-2-2), and each control body (1-2-1) comprises a cylindrical boron carbide control rod and a stainless steel ladle shell for coating the cylindrical boron carbide control rod; the control rod assembly box (1-2-3) coaxially surrounds the guide cylinder (1-2-2); the gaps among the control body (1-2-1), the guide cylinder (1-2-2) and the control rod assembly box (1-2-3) are coolant channels.
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| Application Number | Priority Date | Filing Date | Title |
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| CN202110978390.XA CN113793701B (en) | 2021-08-25 | 2021-08-25 | Spiral cross-shaped metal fuel element reactor core |
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| CN202110978390.XA CN113793701B (en) | 2021-08-25 | 2021-08-25 | Spiral cross-shaped metal fuel element reactor core |
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| CN113793701B CN113793701B (en) | 2022-12-09 |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114446496A (en) * | 2022-02-17 | 2022-05-06 | 中国核动力研究设计院 | Ultra-high flux reactor core based on annular fuel element |
| CN116543933A (en) * | 2023-05-29 | 2023-08-04 | 西安交通大学 | Metal fuel matrix heat pipe cooling reactor core structure |
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| JP2017026372A (en) * | 2015-07-17 | 2017-02-02 | 日立Ｇｅニュークリア・エナジー株式会社 | Fast reactor fuel element, fuel assembly and reactor core loading fuel assembly |
| CN110853777A (en) * | 2019-11-07 | 2020-02-28 | 西安交通大学 | Fuel assembly structure for enhancing negative feedback of temperature of gas-cooled fast reactor and reactor core structure |
| CN110853774A (en) * | 2019-11-21 | 2020-02-28 | 中国核动力研究设计院 | Zirconium hydride moderated metal cooling reactor miniaturization design method and reactor |
| CN113299409A (en) * | 2021-04-30 | 2021-08-24 | 西安交通大学 | Small-size villaumite of spiral cross fuel element cools off high temperature reactor core |
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Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2017026372A (en) * | 2015-07-17 | 2017-02-02 | 日立Ｇｅニュークリア・エナジー株式会社 | Fast reactor fuel element, fuel assembly and reactor core loading fuel assembly |
| CN110853777A (en) * | 2019-11-07 | 2020-02-28 | 西安交通大学 | Fuel assembly structure for enhancing negative feedback of temperature of gas-cooled fast reactor and reactor core structure |
| CN110853774A (en) * | 2019-11-21 | 2020-02-28 | 中国核动力研究设计院 | Zirconium hydride moderated metal cooling reactor miniaturization design method and reactor |
| CN113299409A (en) * | 2021-04-30 | 2021-08-24 | 西安交通大学 | Small-size villaumite of spiral cross fuel element cools off high temperature reactor core |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114446496A (en) * | 2022-02-17 | 2022-05-06 | 中国核动力研究设计院 | Ultra-high flux reactor core based on annular fuel element |
| CN114446496B (en) * | 2022-02-17 | 2024-04-23 | 中国核动力研究设计院 | Ultra-high flux reactor core based on annular fuel elements |
| CN116543933A (en) * | 2023-05-29 | 2023-08-04 | 西安交通大学 | Metal fuel matrix heat pipe cooling reactor core structure |
| CN116543933B (en) * | 2023-05-29 | 2024-01-23 | 西安交通大学 | Metal fuel matrix heat pipe cooling reactor core structure |
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