CN116168853A - Hexagon fuel assembly for heat supply pile - Google Patents

Hexagon fuel assembly for heat supply pile Download PDF

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Publication number
CN116168853A
CN116168853A CN202211574916.9A CN202211574916A CN116168853A CN 116168853 A CN116168853 A CN 116168853A CN 202211574916 A CN202211574916 A CN 202211574916A CN 116168853 A CN116168853 A CN 116168853A
Authority
CN
China
Prior art keywords
hexagonal
tube seat
compression spring
plate
fuel assembly
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
Application number
CN202211574916.9A
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Chinese (zh)
Inventor
何晓军
邹远方
胡立强
李凯
史宝磊
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China Institute of Atomic of Energy
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China Institute of Atomic of Energy
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Publication date
Application filed by China Institute of Atomic of Energy filed Critical China Institute of Atomic of Energy
Priority to CN202211574916.9A priority Critical patent/CN116168853A/en
Publication of CN116168853A publication Critical patent/CN116168853A/en
Pending legal-status Critical Current

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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
    • G21C3/33—Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent 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
    • G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/14—Moderator or core structure; Selection of materials for use as moderator characterised by shape
    • G21C5/16—Shape of its constituent parts
    • 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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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention relates to the technical field of nuclear fuel assemblies, and particularly discloses a hexagonal fuel assembly for a heat supply stack, wherein the plane of the upper end of an upper compression spring is contacted with a compression plate at the uppermost end of a hexagonal upper tube seat, the compression plate is contacted with an upper grid plate of a reactor core, the upper compression spring is sleeved outside a control rod guide tube, and the lower end of the upper compression spring is propped against a bottom plate of the hexagonal upper tube seat and can axially compress the hexagonal upper tube seat and lower parts thereof; the lower end plane of the lower compression spring is contacted with the compression plate at the lowest end of the hexagonal lower tube seat, the compression plate is contacted with the lower grid plate of the reactor core, the lower compression spring is sleeved outside the control rod guide tube, and the upper end of the lower compression spring is propped against the bottom plate of the hexagonal lower tube seat, so that the hexagonal lower tube seat and parts above the hexagonal lower tube seat can be axially supported. When an earthquake happens, the vibration transmitted to the fuel assembly by the reactor core is absorbed by a part of the upper compression spring and the lower compression spring, so that the earthquake resistance of the whole assembly under the earthquake condition is effectively improved.

Description

Hexagon fuel assembly for heat supply pile
Technical Field
The invention belongs to the technical field of nuclear fuel assemblies, and particularly relates to a hexagonal fuel assembly for a heat supply stack.
Background
Nuclear energy is one of the more mature methods to replace primary energy as a safe and clean energy source. A great deal of research has been carried out on the aspect of utilizing nuclear energy to supply heat for areas, pollution emission can be reduced compared with the traditional heat source, heat supply safety is guaranteed, the energy structure of China is effectively improved, the situation of serious energy supply shortage is relieved, and the method has positive significance for protecting the environment, protecting the health of people, relieving the transportation pressure of fire coal and the like.
During operation of a nuclear power plant reactor, the performance of the nuclear fuel is an important factor affecting the safety and economy of the reactor. Therefore, the research of the fuel element is put in a very prominent position all the time internationally, and various performances of the nuclear fuel element are continuously improved by optimizing the design of the fuel element, adopting advanced structural materials, improving the manufacturing process of the element and the like, so that the nuclear power is promoted to develop towards safer and more economical directions. For large pressurized water reactor fuel assemblies, the shock resistance requirement is generally 0.3g acceleration, while for heating reactor fuel assemblies with larger site selection ranges, the shock resistance requirement is higher and is 0.6g acceleration to adapt to various site selection ranges.
Therefore, it is necessary to design a new hexagonal fuel assembly, which has advantages over the conventional square fuel assembly in terms of the anti-seismic performance and the stability of the components of the overall structure, so as to meet the requirements of the heat supply stack on the fuel assembly.
Disclosure of Invention
The invention aims to provide a hexagonal fuel assembly for a heat supply pile, which can improve the performance of the fuel assembly in shock resistance.
The technical scheme of the invention is as follows:
a hexagonal fuel assembly for a heat supply stack comprises a lower compression spring, a hexagonal lower tube seat, a positioning grid, an annular fuel rod, a hexagonal upper tube seat, an upper compression spring and a control rod guide tube;
the hexagonal upper tube seat and the hexagonal lower tube seat are respectively connected with the upper end and the lower end of the control rod guide tube;
the positioning grid is welded on the control rod guide tube;
the annular fuel rods are inserted into cells of the positioning grid and clamped by cell springs, the lower end plugs of the annular fuel rods are fixed on the hexagonal lower tube seats, and the upper end plugs are in a free relaxation state;
the upper end plane of the upper compression spring is contacted with a compression plate at the uppermost end of the hexagonal upper tube seat, the compression plate is contacted with an upper grid plate of the reactor core, the upper compression spring is sleeved outside the control rod guide tube, the lower end of the upper compression spring is propped against the bottom plate of the hexagonal upper tube seat, and the hexagonal upper tube seat and the lower parts thereof can be axially compressed;
the lower end plane of the lower compression spring is contacted with the compression plate at the lowest end of the hexagonal lower tube seat, the compression plate is contacted with the lower grid plate of the reactor core, the lower compression spring is sleeved outside the control rod guide tube, and the upper end of the lower compression spring is propped against the bottom plate of the hexagonal lower tube seat, so that the hexagonal lower tube seat and parts above the hexagonal lower tube seat can be axially supported.
The positioning grid is hexagonal in shape and consists of an outer strip and triangular grid elements;
wherein, the triangle cells are welded with each other to form a hexagonal egg-shaped structure, and the outer strip is welded at the periphery of the egg-shaped structure.
The hexagonal upper tube seat and the hexagonal lower tube seat respectively comprise a hexagonal splitter plate, side rib plates and a sleeve.
The hexagonal lower tube seat and the hexagonal upper tube seat have the same structure and opposite directions.
The pipe diameter of the control rod guide pipe is 1.1-1.5 times of that of the square fuel assembly guide pipe.
In a loose state, the upper end of the upper compression spring and the compression plate of the hexagonal upper tube seat are positioned beyond the upper end of the control rod guide tube;
under the compaction state, the upper grid plate of the reactor core is pressed on the upper end plane of the compaction plate until the upper ends of the compaction plate and the upper ends of the upper compaction springs are flush with the upper ends of the control rod guide pipes.
In a loose state, the lower ends of the lower compression springs and the compression plates of the hexagonal lower tube seat are beyond the lower ends of the control rod guide tubes;
under the compression state, the reactor core lower grid plate is pressed on the lower end plane of the compression plate until the lower ends of the compression plate and the lower end of the lower compression spring are flush with the lower end of the control rod guide tube.
The upper compression spring and the lower compression spring are long cylindrical springs.
The number of the annular fuel rods is determined by the sectional area of the hexagonal fuel assembly and the sectional area of the annular fuel rods, and then the annular fuel rods are obtained through thermal physical calculation;
the number of the control rod guide pipes is consistent with the number of the control rods, and the number of the control rods is obtained through physical calculation.
Is suitable for heat supply piles and meets the 0.6g acceleration earthquake-resistant requirement.
The invention has the remarkable effects that:
(1) According to the hexagonal fuel assembly, due to the action of the elastic pieces such as the upper compression spring and the lower compression spring, when an earthquake happens, the vibration conducted to the fuel assembly by the reactor core can be absorbed by a part of the upper compression spring and the lower compression spring, so that the earthquake resistance of the whole assembly under the earthquake condition is improved.
(2) The control rod guide pipe of the hexagonal fuel assembly has large pipe diameter, high pipe wall thickness and high strength, and can ensure the smooth insertion of the control assembly under the accident condition and realize safe shutdown.
(3) The hexagonal fuel assembly of the invention is also applied with the hexagonal upper tube seat, the positioning grid, the hexagonal lower tube seat and the like besides the compression spring, thereby realizing the uniform symmetry of the assembly structure and ensuring the replaceability of the fuel assembly at all positions of the reactor core.
(4) The hexagonal fuel assembly of the present invention has a larger and denser number of fuel rods than the conventional pressurized water reactor quadrilateral fuel assembly in terms of unit cross section of the fuel assembly, and the hexagonal fuel assembly has a larger strength than the quadrilateral fuel assembly under the same condition in view of the fact that the fuel rods are also important components of the strength of the fuel assembly.
Drawings
FIG. 1 is a hexagonal fuel assembly of 157 fuel rods in an embodiment.
In the figure: 1. the fuel injector comprises a hexagonal upper tube seat, an upper compression spring, a hexagonal lower tube seat, a lower compression spring, a positioning grid, an annular fuel rod and a control rod guide tube.
Detailed Description
The invention will be described in further detail with reference to the accompanying drawings and specific examples.
A hexagonal fuel assembly for a heat supply pile comprises a lower compression spring, a hexagonal lower tube seat, a positioning grid, an annular fuel rod, a hexagonal upper tube seat, an upper compression spring and a control rod guide tube.
The hexagonal upper tube seat consists of a hexagonal flow dividing plate, side rib plates, a sleeve and other parts, and the hexagonal lower tube seat has the same structure as the hexagonal upper tube seat and opposite directions.
The upper compression spring and the lower compression spring are long cylindrical springs.
The outer shape of the positioning grid is hexagonal, and the positioning grid consists of an outer strip and triangular cells, wherein the triangular cells are welded with each other to form a hexagonal egg-shaped structure, and the outer strip is welded at the periphery of the egg-shaped structure.
The annular fuel rod is a fuel rod having upper and lower end plugs, inner and outer cladding and annular pellets.
The control rod guide pipe is a hollow pipe, and compared with the guide pipe of the square fuel assembly, the pipe diameter of the control rod guide pipe is larger and can be 1.1-1.5 times of that of the guide pipe of the square fuel assembly, the pipe wall is thicker, and the strength is higher.
The hexagonal upper tube seat and the hexagonal lower tube seat are respectively connected with the upper end and the lower end of the control rod guide tube; the positioning grid is welded on the control rod guide tube, and the positioning grid, the hexagonal upper tube seat, the hexagonal lower tube seat and the control rod guide tube form a fuel framework together; the annular fuel rods are inserted into cells of the spacer grid and clamped by cell springs, the lower end plugs of the annular fuel rods are fixed on the hexagonal lower tube seat through the lower end plug connecting pieces, and the upper end plugs are in a free loose state.
The upper end plane of the upper compression spring is contacted with a circular perforated compression plate at the uppermost end of the hexagonal upper tube seat, the compression plate is contacted with an upper grid plate of the reactor core, the inner ring of the upper compression spring is contacted with the outer wall of the control rod guide tube, and the lower end of the upper compression spring is propped against the bottom plate of the hexagonal upper tube seat, so that the hexagonal upper tube seat and the parts below the hexagonal upper tube seat can be axially compressed. In a loose state, the upper end of the upper compression spring and the compression plate of the hexagonal upper tube seat are positioned beyond the upper end of the control rod guide tube; under the compaction state, the upper grid plate of the reactor core is pressed on the upper end plane of the compaction plate until the upper ends of the compaction plate and the upper ends of the upper compaction springs are flush with the upper ends of the control rod guide pipes.
The lower end plane of the lower compression spring is contacted with a circular perforated compression plate at the lowest end of the hexagonal lower tube seat, the compression plate is contacted with a reactor core lower grid plate, the inner ring of the lower compression spring is contacted with the outer wall of the control rod guide tube, and the upper end of the lower compression spring is propped against the bottom plate of the hexagonal lower tube seat, so that the hexagonal lower tube seat and parts above the hexagonal lower tube seat can be axially supported. In a loose state, the lower ends of the lower compression springs and the compression plates of the hexagonal lower tube seat are beyond the lower ends of the control rod guide tubes; under the compression state, the reactor core lower grid plate is pressed on the lower end plane of the compression plate until the lower ends of the compression plate and the lower end of the lower compression spring are flush with the lower end of the control rod guide tube.
Because the upper compression spring and the lower compression spring are respectively sleeved outside the control rod guide tube, the guide effect of the outer wall of the control rod guide tube ensures that the control rod guide tube can not generate radial displacement under vibration, and only slightly vibrates in the axial direction. Meanwhile, the inner wall of the control rod guide pipe has a guide effect on the control rod assembly in the pile, so that the control rod can be smoothly inserted under the accident condition, and the safe shutdown is realized.
The hexagonal fuel assembly is suitable for a reactor with higher requirements on the earthquake resistance of the fuel assembly, such as a heat supply reactor, and the earthquake resistance requirement is generally 0.6g acceleration and is far higher than the earthquake resistance requirement of 0.3g of a large commercial pressurized water reactor.
Examples
The hexagonal fuel assembly for the heat supply pile is shown in fig. 1, and consists of a hexagonal upper tube seat 1, an upper compression spring 2, a hexagonal lower tube seat 3, a lower compression spring 4, a positioning grid 5, 157 annular fuel rods 6 and 12 control rod guide tubes 7; or comprises a hexagonal upper tube seat 1, an upper compression spring 2, a hexagonal lower tube seat 3, a lower compression spring 4, a spacer grid 5, 56 annular fuel rods 6 and 6 control rod guide tubes 7.
The number of the annular fuel rods 6 is obtained through a series of thermodynamic physical calculations after the sectional areas of the hexagonal fuel assemblies and the sectional areas of the annular fuel rods 6 are determined; the number of control rods is obtained according to physical calculation, and the control rod guide pipes 7 are consistent with the number of control rods.
While the fundamental principles, principal features, and advantages of the present invention have been shown and described, it will be apparent to those skilled in the art that the present invention is not limited to the details of the foregoing exemplary embodiments, but may be embodied in other specific forms without departing from the spirit or essential characteristics thereof. The present embodiments are, therefore, to be considered in all respects as illustrative and not restrictive, the scope of the invention being indicated by the appended claims rather than by the foregoing description, and all changes which come within the meaning and range of equivalency of the claims are therefore intended to be embraced therein.

Claims (10)

1. A hexagonal fuel assembly for a heating stack, characterized by: comprises a lower compression spring, a hexagonal lower tube seat, a positioning grid, an annular fuel rod, a hexagonal upper tube seat, an upper compression spring and a control rod guide tube;
the hexagonal upper tube seat and the hexagonal lower tube seat are respectively connected with the upper end and the lower end of the control rod guide tube;
the positioning grid is welded on the control rod guide tube;
the annular fuel rods are inserted into cells of the positioning grid and clamped by cell springs, the lower end plugs of the annular fuel rods are fixed on the hexagonal lower tube seats, and the upper end plugs are in a free relaxation state;
the upper end plane of the upper compression spring is contacted with a compression plate at the uppermost end of the hexagonal upper tube seat, the compression plate is contacted with an upper grid plate of the reactor core, the upper compression spring is sleeved outside the control rod guide tube, the lower end of the upper compression spring is propped against the bottom plate of the hexagonal upper tube seat, and the hexagonal upper tube seat and the lower parts thereof can be axially compressed;
the lower end plane of the lower compression spring is contacted with the compression plate at the lowest end of the hexagonal lower tube seat, the compression plate is contacted with the lower grid plate of the reactor core, the lower compression spring is sleeved outside the control rod guide tube, and the upper end of the lower compression spring is propped against the bottom plate of the hexagonal lower tube seat, so that the hexagonal lower tube seat and parts above the hexagonal lower tube seat can be axially supported.
2. A hexagonal fuel assembly for a heating stack as set forth in claim 1 wherein: the positioning grid is hexagonal in shape and consists of an outer strip and triangular grid elements;
wherein, the triangle cells are welded with each other to form a hexagonal egg-shaped structure, and the outer strip is welded at the periphery of the egg-shaped structure.
3. A hexagonal fuel assembly for a heating stack as set forth in claim 1 wherein: the hexagonal upper tube seat and the hexagonal lower tube seat respectively comprise a hexagonal splitter plate, side rib plates and a sleeve.
4. A hexagonal fuel assembly for a heating stack as claimed in claim 3, wherein: the hexagonal lower tube seat and the hexagonal upper tube seat have the same structure and opposite directions.
5. A hexagonal fuel assembly for a heating stack as set forth in claim 1 wherein: the pipe diameter of the control rod guide pipe is 1.1-1.5 times of that of the square fuel assembly guide pipe.
6. A hexagonal fuel assembly for a heating stack as set forth in claim 1 wherein: in a loose state, the upper end of the upper compression spring and the compression plate of the hexagonal upper tube seat are positioned beyond the upper end of the control rod guide tube;
under the compaction state, the upper grid plate of the reactor core is pressed on the upper end plane of the compaction plate until the upper ends of the compaction plate and the upper ends of the upper compaction springs are flush with the upper ends of the control rod guide pipes.
7. A hexagonal fuel assembly for a heating stack as set forth in claim 1 wherein: in a loose state, the lower ends of the lower compression springs and the compression plates of the hexagonal lower tube seat are beyond the lower ends of the control rod guide tubes;
under the compression state, the reactor core lower grid plate is pressed on the lower end plane of the compression plate until the lower ends of the compression plate and the lower end of the lower compression spring are flush with the lower end of the control rod guide tube.
8. A hexagonal fuel assembly for a heating stack as set forth in claim 1 wherein: the upper compression spring and the lower compression spring are long cylindrical springs.
9. A hexagonal fuel assembly for a heating stack as set forth in claim 1 wherein: the number of the annular fuel rods is determined by the sectional area of the hexagonal fuel assembly and the sectional area of the annular fuel rods, and then the annular fuel rods are obtained through thermal physical calculation;
the number of the control rod guide pipes is consistent with the number of the control rods, and the number of the control rods is obtained through physical calculation.
10. A hexagonal fuel assembly for a heating stack according to any one of claims 1 to 9, wherein: is suitable for heat supply piles and meets the 0.6g acceleration earthquake-resistant requirement.
CN202211574916.9A 2022-12-08 2022-12-08 Hexagon fuel assembly for heat supply pile Pending CN116168853A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202211574916.9A CN116168853A (en) 2022-12-08 2022-12-08 Hexagon fuel assembly for heat supply pile

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202211574916.9A CN116168853A (en) 2022-12-08 2022-12-08 Hexagon fuel assembly for heat supply pile

Publications (1)

Publication Number Publication Date
CN116168853A true CN116168853A (en) 2023-05-26

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ID=86420900

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202211574916.9A Pending CN116168853A (en) 2022-12-08 2022-12-08 Hexagon fuel assembly for heat supply pile

Country Status (1)

Country Link
CN (1) CN116168853A (en)

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