CN114446497B - Ultra-high flux reactor core based on square fuel assembly - Google Patents

Ultra-high flux reactor core based on square fuel assembly Download PDF

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Publication number
CN114446497B
CN114446497B CN202210148061.7A CN202210148061A CN114446497B CN 114446497 B CN114446497 B CN 114446497B CN 202210148061 A CN202210148061 A CN 202210148061A CN 114446497 B CN114446497 B CN 114446497B
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fuel
assemblies
reactor core
fuel assemblies
row
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CN114446497A (en
Inventor
蔡云
王连杰
汪量子
夏榜样
余红星
娄磊
张斌
张策
肖鹏
谢运利
刘勇
王星博
唐霄
吉文浩
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Nuclear Power Institute of China
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Nuclear Power Institute of China
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02—Details
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/04—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
    • G21C15/06—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material in fuel elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/10—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from reflector or thermal shield
    • 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
    • G21C3/322—Means to influence the coolant flow through or around the bundles
    • 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 discloses an ultra-high flux reactor core based on a square fuel assembly, which relates to the technical field of nuclear reactors, and has the technical scheme that: the reactor core active region is provided with a central pore passage region, a plurality of fuel assemblies and a plurality of control rod assemblies, wherein the central pore passage region is filled with coolant to form the central pore passage assembly; the sections of the fuel assembly, the control rod assembly and the central pore canal assembly are square; a plurality of the fuel assemblies are compactly arranged, a plurality of control rod assemblies are arranged at the periphery of the active region, and a central orifice assembly is positioned at the center of the active region of the reactor core. The reactor core of the invention has high advancement and competitiveness under the conditions that the thermal power is not more than 200MW, the refueling period is not less than 100 full power days, and the average power density of the reactor core is not more than 1200MW/m 3, and the maximum neutron flux of the reactor core is more than 1X 10 16n/cm2/s.

Description

Ultra-high flux reactor core based on square fuel assembly
Technical Field
The present invention relates to the field of nuclear reactor technology, and more particularly, to an ultra-high flux reactor core based on square fuel assemblies.
Background
The development of nuclear power engineering is not separated from the nuclear reactor, while the development of nuclear reactor is not separated from the test stack. The test stack plays a very important role in the development of various reactor types. The high neutron flux engineering test stack is one of important marks of national science and technology reality, and is an essential infrastructure and an important tool for independent and autonomous nuclear energy development in China. The ultra-high flux test stack can be built to solve the problems of low neutron flux level and insufficient irradiation test capability of the current test research nuclear facilities in China, and can solve the problem that the core structural material of the current advanced nuclear energy and nuclear technology in China is seriously dependent on import abroad. These all depend on the neutron flux level of the test stack, and the higher the neutron flux, the better the irradiation and isotope production, etc.
Currently, internationally established advanced test stacks have a neutron flux on the order of 1.0X10 15n/cm2/s, with very few test stacks having a flux exceeding 2.0X10 15n/cm2/s. Typical advanced test stacks are the China advanced research stacks (CARR stacks) and the French JHR stacks. The CARR stack adopts U 3Si2 -Al dispersed flat fuel, square box fuel components form square grids, the U-235 enrichment degree is 20%, and the core uranium density is 4.0gU/cm 3. Be is filled between the reactor core container and the fuel assembly, and a heavy water reflecting layer annular water tank is arranged outside the reactor core container. The JHR pile adopts U 3Si2 -Al cylindrical fuel and a daisy type grid arrangement mode, the U-235 enrichment degree is 27%, and the core uranium density is 4.8gU/cm 3. Be is selected as the reflecting layer on the periphery of the reactor core.
New generation advanced test stack designs gradually employ fourth generation stack types, such as russian projected build high flux stack MBIR, which is a sodium cooled fast stack concept with a thermal power of 150MW and a maximum fast neutron flux level of 5.3 x 10 15n/cm2/s. The national laboratory of the archery is currently working on developing a conceptual design of irradiation test stacks known as multifunctional test stacks (VTR). VTR is a sodium cooled fast reactor concept with a reactor thermal power of 300MW and a maximum fast neutron flux level of 4.0 x 10 15n/cm2/s; the reflective layer design of the existing novel test stack is generally made of depleted uranium or stainless steel materials, and the integral neutron flux level is limited. Therefore, it is of great significance to study and design an ultra-high flux reactor core based on square fuel assemblies that overcomes the above-mentioned drawbacks.
Disclosure of Invention
In order to solve the defects in the prior art, the invention aims to provide an ultrahigh flux reactor core based on square fuel assemblies, and the development of material irradiation test is greatly improved under the condition that the thermal power is not more than 200MW, the refueling period is not less than 100 full power days, the average assembly power density is not more than 1200MW/m 3, and the maximum neutron flux in the reactor core is more than 1X 10 16n/cm2/s, so that the important and scarce isotope production problem in China is solved.
The technical aim of the invention is realized by the following technical scheme: the ultra-high flux reactor core based on the square fuel assemblies comprises a reflecting layer and a core active area arranged in the reflecting layer, wherein the core active area is provided with a central pore canal area, a plurality of fuel assemblies and a plurality of control rod assemblies, and the central pore canal area is filled with coolant to form the central pore canal assembly;
The sections of the fuel assembly, the control rod assembly and the central pore canal assembly are square;
A plurality of the fuel assemblies are compactly arranged, a plurality of control rod assemblies are arranged at the periphery of the core active area, and a central orifice assembly is positioned at the center of the core active area.
Further, the active area of the reactor core is provided with fifty-two fuel assemblies, eight control rod assemblies and a central duct assembly;
The fuel assemblies, the control rod assemblies and the central duct assemblies in the reactor core active area are arranged in the row and column directions identically, and the specific arrangement is as follows: the first row has three fuel assemblies, the second row has four fuel assemblies and three control rod assemblies, the third row has seven fuel assemblies, the fourth row has nine fuel assemblies, the fifth row has six fuel assemblies, two control rod assemblies and a central bore assembly, the sixth row has nine fuel assemblies, the seventh row has seven fuel assemblies, the eighth row has four fuel assemblies and three control rod assemblies, and the ninth row has three fuel assemblies;
The eight control rod assemblies are positioned at eight peripheral crossing positions of the second row, the fifth row and the eighth row with the second column, the fifth column and the eighth column respectively.
Further, the fuel assembly includes a fuel plate and a structural plate;
the fuel plates are stacked at equal intervals, and cooling flow channels for coolant to flow are formed between the adjacent fuel plates;
the structure plates are distributed on two sides of the fuel plates and are used for symmetrically fixing a plurality of fuel plates;
the fuel plate is composed of a fuel core and a fuel cladding, the fuel core being located within the fuel cladding.
Further, the width of the cooling flow channel along the adjacent fuel plates is 2.5mm-3.5mm.
Furthermore, the fuel component is prepared from any one metal fuel of U-Zr, U-Mo and U-Pu-Zr.
Further, the thickness of the fuel core body is 0.5-1.5mm, and the thickness of the fuel cladding is 0.2-0.5 mm.
Further, the control rod assembly comprises an air gap, an absorber, an air gap, a guide pipe and a cooling flow channel which are sequentially arranged from inside to outside;
the absorber is in an annular shape and is prepared from a boron carbide material;
the guide tube is made of stainless steel materials;
the cooling flow passage is filled with a coolant.
Further, the outer shape of the reflecting layer in the radial direction is circular, and the outer diameter of the reflecting layer is not smaller than 2500mm.
Further, the height of the reactor core active area is 400mm-600mm, and the thickness of the reflecting layer at the two ends of the reactor core active area is 500mm-1000mm.
Further, the maximum neutron flux in the reactor core exceeds 1X 10 16n/cm2/s under the condition that the thermal power is not more than 200MW, the refueling period is not less than 100 full power days and the average assembly power density is not more than 1200MW/m 3.
Compared with the prior art, the invention has the following beneficial effects:
1. The ultra-high flux reactor core based on the square fuel assembly provided by the invention has the advantages that the maximum neutron flux of the reactor core is 1 multiplied by 10 16n/cm2/s under the conditions that the thermal power of the reactor core is not more than 200MW, the refueling period is not less than 100 full power days, and the average power density of the reactor core is not more than 1200MW/m 3, and the maximum neutron flux of the reactor core is far higher than that of the currently-constructed or planned reactor, so that the reactor core has very high advancement and competitiveness;
2. the cooling flow channels arranged between the fuel plates are wider, and the coolant can effectively carry away the heat of the reactor core;
3. the invention designs the area size of the reflecting layer, is beneficial to developing various researches, such as arranging pore channels and loops for various purposes, and simultaneously, a large amount of coolant in the reflecting layer is beneficial to ensuring the safety of the reactor core because the reflecting layer material and the coolant.
Drawings
The accompanying drawings, which are included to provide a further understanding of embodiments of the application and are incorporated in and constitute a part of this specification, illustrate embodiments of the application and together with the description serve to explain the principles of the application. In the drawings:
FIG. 1 is a schematic diagram of the distribution of core loading in an embodiment of the invention;
FIG. 2 is a schematic axial view of a core in an embodiment of the invention.
FIG. 3 is a schematic illustration of the structure of a fuel assembly in an embodiment of the invention;
FIG. 4 is a schematic view of the structure of a fuel plate in an embodiment of the invention;
FIG. 5 is a schematic view of the structure of a control rod assembly in accordance with an embodiment of the present invention;
In the drawings, the reference numerals and corresponding part names:
1. A fuel plate; 2. a structural panel; 3. a cooling flow passage; 4. a fuel cladding; 5. a fuel core; 6. an absorber; 7. a guide tube; 8. a reflective layer; 9. a control rod assembly; 10. a fuel assembly; 11. a core active region.
Detailed Description
For the purpose of making apparent the objects, technical solutions and advantages of the present invention, the present invention will be further described in detail with reference to the following examples and the accompanying drawings, wherein the exemplary embodiments of the present invention and the descriptions thereof are for illustrating the present invention only and are not to be construed as limiting the present invention.
It will be understood that when an element is referred to as being "mounted" or "disposed" on another element, it can be directly on the other element or be indirectly on the other element. When an element is referred to as being "connected to" another element, it can be directly or indirectly connected to the other element.
It is to be understood that the terms "length," "width," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," and the like are merely for convenience in describing and simplifying the description based on the orientation or positional relationship shown in the drawings, and do not indicate or imply that the devices or elements referred to must have a particular orientation, be constructed and operated in a particular orientation, and thus are not to be construed as limiting the invention.
Furthermore, the terms "first," "second," and the like, are used for descriptive purposes only and are not to be construed as indicating or implying a relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defining "a first" or "a second" may explicitly or implicitly include one or more such feature. In the description of the present invention, the meaning of "a plurality" is two or more, unless explicitly defined otherwise.
Examples: the ultra-high flux reactor core based on square fuel assemblies, as shown in fig. 1 and 2, comprises a reflecting layer 8 and a core active area 11 arranged in the reflecting layer 8, wherein the core active area 11 is provided with a central duct area, a plurality of fuel assemblies 10 and a plurality of control rod assemblies 9, the central duct area is filled with coolant to form a central duct assembly, and liquid lead or liquid lead bismuth is used for cooling. The fuel assembly 10, the control rod assembly 9 and the central tunnel assembly are all square in cross-section. The plurality of fuel assemblies 10 are compactly arranged to reduce core leakage. A plurality of control rod assemblies 9 are arranged at the periphery of the active region 11 of the core to control the power distribution of the peripheral assemblies and to increase the power density of the fuel assemblies 10 in the central region, which is beneficial to increasing the maximum neutron flux density of the core. And the central orifice assembly is located in the center of the core active zone 11.
As shown in fig. 1, the core active zone 11 is provided with fifty-two fuel assemblies 10, eight control rod assemblies 9, and one central orifice assembly. The arrangement of the fuel assemblies 10, the control rod assemblies 9 and the central tunnel assemblies in the core active zone 11 along the row and column directions is the same, and the specific arrangement is as follows: the first row has three fuel assemblies 10, the second row has four fuel assemblies 10 and three control rod assemblies 9, the third row has seven fuel assemblies 10, the fourth row has nine fuel assemblies 10, the fifth row has six fuel assemblies 10, two control rod assemblies 9 and one central bore assembly, the sixth row has nine fuel assemblies 10, the seventh row has seven fuel assemblies 10, the eighth row has four fuel assemblies 10 and three control rod assemblies 9, and the ninth row has three fuel assemblies 10; eight control rod assemblies 9 are located at eight peripheral intersections of the second, fifth and eighth rows with the second, fifth and eighth columns, respectively.
As shown in fig. 3 and 4, the fuel assembly 10 includes a fuel plate 1 and a structural plate 2 made of stainless steel; a plurality of fuel plates 1 are stacked at equal intervals, and cooling flow channels 3 for coolant to flow are formed between adjacent fuel plates 1; the structural plates 2 are distributed on two sides of the fuel plate 1 and are used for symmetrically fixing a plurality of fuel plates 1; the fuel plate 1 is composed of a fuel core 5 and a fuel cladding 4, the fuel core 5 being located within the fuel cladding 4.
As shown in fig. 3, the cooling flow channels 3 have a width of 2.5mm to 3.5mm along the adjacent fuel plates 1. The cooling flow channels 3 arranged between the fuel plates 1 and the fuel plates 1 are wider, and the coolant can effectively carry away heat of the reactor core.
The fuel assembly 10 is made of any one of U-Zr, U-Mo and U-Pu-Zr metal fuel, and the fuel containing Pu is beneficial to improving the maximum neutron flux density. The thickness of the fuel core 5 is 0.5-1.5mm, preferably 0.9mm. The fuel cladding 4 has a thickness of 0.2mm-0.5mm.
As shown in fig. 5, the control rod assembly 9 includes an air gap, an absorber 6, an air gap, a guide pipe 7 and a cooling flow passage 3 which are disposed in this order from the inside to the outside; the absorber 6 is in a ring shape and is made of boron carbide material; the guide tube 7 is made of stainless steel materials; the cooling flow channel 3 is filled with a coolant.
As shown in fig. 1 and 2, the outer shape of the reflective layer 8 in the radial direction is circular, and the outer diameter of the reflective layer 8 is not less than 2500mm. The height of the core active zone 11 is 400mm-600mm, preferably 500mm. The thickness of the reflecting layer 8 at the two ends of the reactor core active area 11 is 500mm-1000mm, and the lower height of the active area is beneficial to reducing the maximum cladding temperature and is more beneficial to the reactor core safety.
In this embodiment, the maximum outer diameter of the radial reflective layer 8 is 3000mm, and both the axial upper reflective layer 8 and the lower reflective layer 8 are 1000mm thick.
It should be noted that, the reflecting layer 8 is made of the same material as the coolant, i.e. liquid lead or liquid lead bismuth, and occupies a larger area in the axial and radial arrangement, which is beneficial to reducing core leakage and simultaneously beneficial to arranging various channels and loops in the reflecting layer 8; the central tunnel region may be used as a material irradiation test, isotope production, or as a control rod passage for emergency shutdown, the central tunnel being formed of coolant.
As shown in fig. 1, for a core of 52-cartridge fuel assemblies 10, the thermal power is 200MW, the loading period is 100 full power days, the maximum neutron flux during the loading period is 1.08 x 10 16n/cm2/s, and the average assembly power density is 1100MW/m 3.
Working principle: the maximum neutron flux of the reactor core is 1 multiplied by 10 16n/cm2/s under the conditions that the thermal power is not more than 200MW, the refueling period is not less than 100 full power days and the average power density of the reactor core is not more than 1200MW/m 3, and the maximum neutron flux of the reactor core is far higher than that of a currently-established or planned reactor, so that the reactor core has high advancement and competitiveness.
The foregoing description of the embodiments has been provided for the purpose of illustrating the general principles of the invention, and is not meant to limit the scope of the invention, but to limit the invention to the particular embodiments, and any modifications, equivalents, improvements, etc. that fall within the spirit and principles of the invention are intended to be included within the scope of the invention.

Claims (9)

1. The ultra-high flux reactor core based on square fuel assemblies comprises a reflecting layer (8) and a core active area (11) arranged in the reflecting layer (8), and is characterized in that the core active area (11) is provided with a central pore canal area, a plurality of fuel assemblies (10) and a plurality of control rod assemblies (9), and the central pore canal area is filled with coolant to form the central pore canal assembly;
The sections of the fuel assembly (10), the control rod assembly (9) and the central pore canal assembly are square;
A plurality of the fuel assemblies (10) are compactly arranged, a plurality of control rod assemblies (9) are arranged at the periphery of the reactor core active area (11), and a central pore canal assembly is positioned at the center of the reactor core active area (11);
The reactor core active area (11) is provided with fifty-two fuel assemblies (10), eight control rod assemblies (9) and a central duct assembly;
The arrangement of the fuel assemblies (10), the control rod assemblies (9) and the central duct assemblies in the reactor core active area (11) along the row and column directions is the same, and the specific arrangement is as follows: the first row has three fuel assemblies (10), the second row has four fuel assemblies (10) and three control rod assemblies (9), the third row has seven fuel assemblies (10), the fourth row has nine fuel assemblies (10), the fifth row has six fuel assemblies (10), two control rod assemblies (9) and one central bore assembly, the sixth row has nine fuel assemblies (10), the seventh row has seven fuel assemblies (10), the eighth row has four fuel assemblies (10) and three control rod assemblies (9), and the ninth row has three fuel assemblies (10);
eight control rod assemblies (9) are positioned at the positions of eight peripheral intersections of the second row, the fifth row and the eighth row with the second column, the fifth column and the eighth column respectively.
2. The ultra-high flux reactor core based on square fuel assemblies of claim 1, wherein the fuel assemblies (10) comprise fuel plates (1) and structural plates (2);
The fuel plates (1) are stacked at equal intervals, and cooling flow channels (3) for flowing the coolant are formed between the adjacent fuel plates (1);
the structure plates (2) are distributed on two sides of the fuel plates (1) and are used for symmetrically fixing a plurality of fuel plates (1);
the fuel plate (1) consists of a fuel core body (5) and a fuel cladding (4), wherein the fuel core body (5) is positioned in the fuel cladding (4).
3. The ultra-high flux reactor core based on square fuel assemblies as claimed in claim 2, wherein the cooling flow channels (3) are 2.5mm-3.5mm along the width between adjacent fuel plates (1).
4. The ultra-high flux reactor core based on square fuel assemblies of claim 2, wherein the fuel assemblies (10) are prepared from any one of U-Zr, U-Mo, U-Pu-Zr metal fuels.
5. The ultra-high flux reactor core based on square fuel assemblies of claim 2, wherein the thickness of the fuel core (5) is 0.5-1.5mm and the thickness of the fuel cladding (4) is 0.2-0.5 mm.
6. The ultra-high flux reactor core based on square fuel assemblies according to claim 1, characterized in that the control rod assembly (9) comprises an air gap, an absorber (6), an air gap, a guide tube (7) and a cooling runner (3) arranged in sequence from inside to outside;
The absorber (6) is in an annular shape and is prepared from a boron carbide material;
The guide tube (7) is made of stainless steel materials;
The cooling channels (3) are filled with a coolant.
7. The ultra-high flux reactor core based on square fuel assemblies according to any one of claims 1-6, wherein the reflective layer (8) has a circular shape in the radial direction and the reflective layer (8) has an outer diameter of not less than 2500mm.
8. The ultra-high flux reactor core based on square fuel assemblies according to any one of claims 1-6, characterized in that the height of the core active area (11) is 400-600 mm and the thickness of the reflective layers (8) at both ends of the core active area (11) is 500-1000 mm.
9. The ultra-high flux reactor core based on square fuel assemblies of any one of claims 1-6, wherein the ultra-high flux reactor core has a maximum neutron flux in excess of 1 x 10 16n/cm2/s within the core at a thermal power of no more than 200MW, a refueling cycle of no less than 100 full power days, and an average assembly power density of no more than 1200MW/m 3.
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