CN114005554A - Fluoride salt cooling high-temperature reactor core based on spiral cross fuel element - Google Patents

Fluoride salt cooling high-temperature reactor core based on spiral cross fuel element Download PDF

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Publication number
CN114005554A
CN114005554A CN202111230990.4A CN202111230990A CN114005554A CN 114005554 A CN114005554 A CN 114005554A CN 202111230990 A CN202111230990 A CN 202111230990A CN 114005554 A CN114005554 A CN 114005554A
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China
Prior art keywords
reactor core
fuel
spiral cross
assembly
fuel element
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CN202111230990.4A
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Chinese (zh)
Inventor
张大林
周星光
秦浩
王成龙
田文喜
苏光辉
秋穗正
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Xian Jiaotong University
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Xian Jiaotong University
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Priority to CN202111230990.4A priority Critical patent/CN114005554A/en
Publication of CN114005554A publication Critical patent/CN114005554A/en
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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
    • G21C3/326—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
    • G21C3/328—Relative disposition of the elements in the bundle lattice
    • 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
    • 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
    • G21C3/334—Assembling, maintenance or repair of 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
    • G21C3/34—Spacer grids
    • G21C3/3424—Fabrication of spacer grids
    • 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)
  • Carbon And Carbon Compounds (AREA)

Abstract

The invention discloses a fluoride salt cooling high-temperature reactor core based on a spiral cross fuel element, which comprises the following steps: the method comprises the following steps of (1) sizing a spiral cross-shaped fuel element, arranging the fuel element and a control poison in an assembly, arranging a component in a reactor core and arranging radial and axial reflecting layers of the reactor core; the reactor core active area comprises 3 component forms, including a fuel component, a graphite reflecting layer component with a coolant channel and a pure graphite reflecting layer component; the arrangement of each element in the fuel assembly and the arrangement of each assembly in the reactor core are both in hexagonal arrangement; the reactor core designed by the invention has inherent safety, small volume, high fuel consumption and better thermal hydraulic performance; the villiaumite cooling high-temperature reactor energy system based on the reactor core design can provide clean high-temperature process heat for subsequent energy requirements, is beneficial to comprehensive utilization of energy, and improves energy circulation efficiency so as to obtain higher economy.

Description

Fluoride salt cooling high-temperature reactor core based on spiral cross fuel element
Technical Field
The invention relates to the field of nuclear reactor core design, in particular to a fluoride salt cooled high-temperature reactor core based on a spiral cross fuel element.
Background
At present, plate type, rod type and annular fuel elements are mostly adopted in solid fuel molten salt reactors researched at home and abroad, and when the fuel elements are used, a positioning grid frame is required to be adopted for positioning in the radial direction. And the molten salt is used as a high Pr number fluid and has higher viscosity. The fluorine salt generates a large flow resistance when passing through the spacer grid, requiring a large power of the coolant pump to overcome the flow resistance.
Disclosure of Invention
The invention provides a fluoride salt cooling high-temperature reactor core based on a spiral cross fuel element, wherein the spiral cross fuel element can complete self-connection positioning design and enables a coolant to generate transverse mixing to enhance heat exchange, so that a positioning grid frame is not needed in the radial direction, the flow resistance can be reduced, the pump work is reduced, and the overall circulation efficiency of a reactor system is improved.
In order to achieve the purpose, the invention adopts the following technical scheme:
a high temperature reactor core of villaumite cooling based on spiral cross fuel element, the central active area of the reactor core is 19 boxes of fuel assemblies 8, divide into three circles of hexagon and arrange; the outermost layer in the radial direction has 18 coolant passages 9; the remaining part of the whole outer side of the reactor core is a reactor core graphite reflecting layer 10 which is used for reducing neutron leakage and improving the economy; the upper end and the lower end in the longitudinal direction are provided with a coolant reflecting layer 11;
the fuel assembly 8 comprises 66 spiral cross fuel elements 3, 12 graphite sticks 4, 6 control rods 5 and 6 burnable poison rods 6, and an assembly graphite reflecting layer 7 is arranged on the outer layer of the assembly; the arrangement mode of elements in the fuel assembly is six-circle hexagonal arrangement, the first circle is a central guide pipe, and the second circle, the third circle and the fifth circle are all spiral cross-shaped fuel elements; six vertex positions of the fourth circle of hexagons are control rods 5, and the rest positions are graphite rods 4; six vertex positions of the sixth circle of hexagons are burnable poison rods 6, and the rest positions are spiral cross-shaped fuel elements; the spiral cross fuel elements 3 are positioned by self connection, and no positioning grillwork is needed; the elements in the fuel assembly are arranged in a hexagon, and the spiral cross fuel elements can be automatically connected and positioned once twisted by 30 degrees in the axial direction;
the core coolant in the coolant channel 9 is a fluoride salt.
The radius of the reactor core is 150cm, and the height of the reactor core is 400 cm; the radius of the coolant channel 9 is 6 cm; the height of the coolant reflection layer 11 is 50 cm.
The integral structure formed by the fuel assembly 8 and the assembly graphite reflecting layer 7 on the outer layer is the same as the structure of the reactor core graphite reflecting layer 10 with the coolant channel, and the cross sections of the fuel assembly 8 and the reactor core graphite reflecting layer are regular hexagons; hexagonal center distance D in assembly415.89cm, thickness D of graphite reflective layer 7 of the assembly5It was 6.61 cm.
Thickness D of cladding 2 in said spiral cross fuel element 330.8mm, envelope 2 transition radius R17.55mm, petal radius R in cladding 234.45mm, transition radius R of the fuel rod 128.35mm, the overall width D of the spiral cross fuel element 3132.9mm, the center distance D of the petal in the fuel rod 1224mm, the overall length of the spiral cross fuel element 3 is 4 m; in the fuel rod 1, the TRISO particles were dispersed in the graphite matrix at a volume fraction of 50%,235the enrichment of U was 19.75% and the cladding portion 2 was carbon clad.
The control rod 5 and the burnable poison rod 6 are both in-reactor control poisons.
The reactor core thermal power is 125MW, the coolant temperature at the inlet of the reactor core coolant channel 9 is 923K, the outlet temperature is 973K, and the reactor core coolant adopts molten FLiBe, wherein LiF and BeF2The mole fractions of (a) and (b) were 67% and 33%, respectively.
Compared with the existing reactor core, the invention has the following advantages:
1. the spiral cross fuel is positioned by self-connection, and a positioning grid frame is not needed, so that the pumping work is reduced, and the circulation efficiency of a reactor system is improved. The elements in the fuel assembly are arranged in a hexagonal shape, and the spiral cross fuel elements can be automatically connected and positioned once when being twisted for 30 degrees in the axial direction, so that the reactor core structure is more compact, more self-connecting positioning points among the elements are arranged, and the structure is more stable.
2. The reactor core is provided with the graphite reflecting layer and the coolant reflecting layer in the radial direction and the axial direction, so that the neutron leakage rate is reduced, and the reactor core has higher neutron economy.
3. The fuel elements of the reactor core adopt spiral cross fuel elements with larger transition radius, and the direct contact area of the coolant and the fuel elements is increased, so that the heat exchange is enhanced. Meanwhile, the spiral cross fuel element with larger transition radius is adopted, so that the secondary flow of the coolant is easier to occur, the transverse mixing of the coolant is enhanced, and the improvement of the power density of the reactor core is facilitated.
Drawings
FIG. 1 is a schematic cross-sectional view of a villiaumite-cooled high temperature reactor core based on helical cruciform fuel elements of the present invention.
FIG. 2 is a longitudinal section schematic diagram of a villiaumite-cooled high temperature reactor core based on spiral cross fuel elements.
FIG. 3 is a schematic cross-sectional view of the components in a helical cruciform fuel element based villiaumite-cooled high temperature reactor core of the present invention.
FIG. 4 is a schematic perspective view of a spiral cross fuel element based fluoro-salt cooled fuel element in a core of a high temperature reactor of the present invention.
FIG. 5 is a schematic cross-sectional view of a spiral cross fuel element based fluoro-salt cooled high temperature reactor core fuel element of the present invention.
Detailed Description
The invention provides a fluoride salt cooled high temperature reactor core based on spiral cross fuel elements, and the invention is further described in detail by combining the attached drawings.
As shown in fig. 1 and 2, the present embodiment of a villiaumite cooled high temperature reactor core based on spiral cross fuel elements has a total of 19 fuel assemblies 8 arranged in a three-turn hexagonal arrangement. The radius of the core is 150cm, and the height is 400 cm. The outermost layer in the radial direction is provided with 18 coolant channels 9 with the radius of 6 cm; the remaining part of the whole outer side of the reactor core is a reactor core graphite reflecting layer 10 which is used for reducing neutron leakage and improving the economy; the upper and lower ends of the longitudinal direction are respectively provided with a coolant reflecting layer 11 with the height of 50 cm; the core thermal power is 125MW, the coolant temperature at the inlet of the core coolant channel 9 is 923K, the outlet temperature is 973K, and the core coolant is molten FLiBe, wherein the mole fractions of LiF and BeF2 are 67% and 33%, respectively.
As shown in fig. 3, the fuel assembly of the present embodiment has 66 helical cross fuel elements 3, 12 graphite rods 4, 6 control rods 5 and 6 burnable poison rods 6; hexagonal center distance D in assembly415.89cm, the outer layer having a thickness D5A 6.61cm assembly graphite reflective layer 7; the arrangement mode of elements in the fuel assembly is six-circle hexagonal arrangement; the first circle is a central guide pipe, and the second circle, the third circle and the fifth circle are all spiral cross-shaped fuel elements; six vertex positions of the fourth circle of hexagons are control rods 5, and the rest positions are graphite rods 4; six vertex positions of the sixth hexagon are burnable poison rods 6, and other positions are spiral cross-shaped fuel elements. The spiral cross fuel elements 3 are positioned by self connection, and no positioning grillwork is needed; the elements in the fuel assembly are arranged in a hexagon, and the spiral cross fuel elements can be automatically connected and positioned once twisted by 30 degrees in the axial direction;
as shown in fig. 4 and 5, the thickness D3 of the cladding 2 in the spiral cross fuel element 3 of the present embodiment is 0.8mm, the transition radius R1 in the cladding 2 is 7.55mm, the petal radius R3 in the cladding 2 is 4.45mm, the transition radius R2 of the fuel rod is 8.35mm, the overall width D1 of the spiral cross fuel element 3 is 32.9mm, the petal center distance D2 in the fuel rod 1 is 24mm, and the overall length of the spiral cross fuel element 3 is 4 m; in fuel rod 1, the TRISO particles are dispersed in the graphite matrix at a volume fraction of 50%, in the fuel235The enrichment of U was 19.75% and the cladding portion 2 was carbon clad.
As an originalIn the preferred embodiment of the invention, the core thermal power is 125MW, the coolant temperature at the inlet of the core coolant channel 9 is 923K, the outlet temperature is 973K, and the core coolant is molten FLiBe, wherein LiF and BeF2The mole fractions of (a) and (b) were 67% and 33%, respectively.

Claims (6)

1. A villiaumite cooling high temperature reactor core based on spiral cross fuel element which is characterized in that: the reactor core central active area is 19 boxes of fuel assemblies (8) which are arranged in a three-circle hexagonal mode; the outermost layer in the radial direction is provided with 18 coolant channels (9); the remaining part of the whole outer side of the reactor core is a reactor core graphite reflecting layer (10) which is used for reducing neutron leakage and improving the economy; the upper end and the lower end of the longitudinal direction are provided with a coolant reflecting layer (11);
66 spiral cross fuel elements (3), 12 graphite sticks (4), 6 control rods (5) and 6 burnable poison sticks (6) are arranged in the fuel assembly (8), and an assembly graphite reflecting layer (7) is arranged on the outer layer of the assembly; the arrangement mode of elements in the fuel assembly is six-circle hexagonal arrangement, the first circle is a central guide pipe, and the second circle, the third circle and the fifth circle are all spiral cross-shaped fuel elements; six vertex positions of the fourth circle of hexagons are control rods (5), and the rest positions are graphite rods (4); six vertex positions of the sixth circle of hexagons are burnable poison rods (6), and the rest positions are spiral cross-shaped fuel elements; the spiral cross fuel elements (3) are positioned by self connection without a positioning grid; the elements in the fuel assembly are arranged in a hexagon, and the spiral cross fuel elements can be automatically connected and positioned once twisted by 30 degrees in the axial direction;
the core coolant in the coolant channel (9) is a fluoride salt.
2. The helical cruciform fuel element-based villaumite cooled high temperature reactor core of claim 1, wherein: the radius of the reactor core is 150cm, and the height of the reactor core is 400 cm; the radius of the coolant channel (9) is 6 cm; the height of the coolant reflection layer (11) is 50 cm.
3. A spiral cross-shaped fuel element based on claim 1The villiaumite cooling high temperature reactor core is characterized in that: the integral structure formed by the fuel assembly (8) and the assembly graphite reflecting layer (7) on the outer layer is the same as the structure of the reactor core graphite reflecting layer (10) with the coolant channel, and the cross sections of the integral structure are regular hexagons; hexagonal center distance D in assembly415.89cm, thickness D of graphite reflective layer (7) of the assembly5It was 6.61 cm.
4. The helical cruciform fuel element-based villaumite cooled high temperature reactor core of claim 1, wherein: thickness D of cladding (2) in spiral cross fuel element (3)30.8mm, transition radius R in the cladding (2)17.55mm, petal radius R in the cladding (2)34.45mm, transition radius R of the fuel rod (1)28.35mm, the overall width D of the spiral cross fuel element (3)132.9mm, petal center distance D in the fuel rod (1)224mm, the overall length of the spiral cross fuel element (3) is 4 m; in the fuel rod (1), TRISO particles are dispersed in a graphite matrix at a volume fraction of 50%,235the enrichment degree of U is 19.75%, and the cladding part (2) adopts carbon cladding.
5. The helical cruciform fuel element-based villaumite cooled high temperature reactor core of claim 1, wherein: the control rod (5) and the burnable poison rod (6) are both in-reactor control poisons.
6. The helical cruciform fuel element-based villaumite cooled high temperature reactor core of claim 1, wherein: the thermal power of the reactor core is 125MW, the temperature of the coolant at the inlet of the reactor core coolant channel (9) is 923K, the temperature at the outlet of the reactor core coolant channel is 973K, and the reactor core coolant adopts molten FLiBe, wherein LiF and BeF2The mole fractions of (a) and (b) were 67% and 33%, respectively.
CN202111230990.4A 2021-10-22 2021-10-22 Fluoride salt cooling high-temperature reactor core based on spiral cross fuel element Pending CN114005554A (en)

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Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20090252278A1 (en) * 2007-12-26 2009-10-08 Thorium Power, Inc. Nuclear reactor (alternatives), fuel assembly of seed-blanket subassemblies for nuclear reactor (alternatives), and fuel element for fuel assembly
CN102947890A (en) * 2010-05-11 2013-02-27 钍能源股份有限公司 Fuel assembly
CN103493143A (en) * 2010-08-30 2014-01-01 西屋电气有限责任公司 Optimized flower tubes and optimized advanced grid configurations
CN105453184A (en) * 2013-05-10 2016-03-30 钍能源股份有限公司 Fuel assembly
CN113299408A (en) * 2021-04-30 2021-08-24 西安交通大学 Modular small-sized villaumite cooling high-temperature reactor system
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
CN113470840A (en) * 2021-06-21 2021-10-01 清华大学 Method for manufacturing spiral multi-blade nuclear fuel element

Patent Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20090252278A1 (en) * 2007-12-26 2009-10-08 Thorium Power, Inc. Nuclear reactor (alternatives), fuel assembly of seed-blanket subassemblies for nuclear reactor (alternatives), and fuel element for fuel assembly
CN102947890A (en) * 2010-05-11 2013-02-27 钍能源股份有限公司 Fuel assembly
CN103493143A (en) * 2010-08-30 2014-01-01 西屋电气有限责任公司 Optimized flower tubes and optimized advanced grid configurations
CN105453184A (en) * 2013-05-10 2016-03-30 钍能源股份有限公司 Fuel assembly
CN113299408A (en) * 2021-04-30 2021-08-24 西安交通大学 Modular small-sized villaumite cooling high-temperature reactor system
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
CN113470840A (en) * 2021-06-21 2021-10-01 清华大学 Method for manufacturing spiral multi-blade nuclear fuel element

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