CN109192332B - Hexagonal casing type fuel reactor core cobalt target assembly nuclear design inspection reactor core and method - Google Patents
Hexagonal casing type fuel reactor core cobalt target assembly nuclear design inspection reactor core and method Download PDFInfo
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- CN109192332B CN109192332B CN201811069045.9A CN201811069045A CN109192332B CN 109192332 B CN109192332 B CN 109192332B CN 201811069045 A CN201811069045 A CN 201811069045A CN 109192332 B CN109192332 B CN 109192332B
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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
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
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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
Abstract
The invention discloses a hexagonal casing type fuel core cobalt target assembly nuclear design inspection core and a method thereof, wherein the inspection core comprises fuel assemblies, beryllium assemblies, control rod assemblies, cobalt target assemblies and water grid elements, the core is totally arranged at 265 positions, namely 20 boxes of fuel assemblies, 43 boxes of beryllium assemblies, 4 boxes of cobalt target assemblies, 12 control rod assemblies and 186 water grid elements, the 20 boxes of fuel assemblies are intensively arranged in the central area of the core with L12 as the central position, the 43 boxes of beryllium assemblies are arranged around the fuel assemblies at the inner side and the outer side of the fuel assemblies, the 12 control rod assemblies are arranged between the beryllium assemblies and the fuel assemblies at intervals, the 4 boxes of cobalt target assemblies are arranged at the periphery of the fuel assemblies next to the fuel assemblies, and each fuel assembly, beryllium assembly, control rod assembly, cobalt target assembly and water grid element respectively occupy 1 position. The method can meet the requirement of the test nuclear design program on the calculation reliability of the hexagonal sleeve type fuel reactor core cobalt target assembly.
Description
Technical Field
The invention relates to the technical field of nuclear reactor design, in particular to a hexagonal casing type fuel reactor core cobalt target assembly nuclear design inspection reactor core and a method.
Background
The development of nuclear reactors cannot be separated from test reactors, and the test reactors play an important role in the development of various reactor types. The development trend of the advanced test reactor is to have high thermal neutron or fast neutron fluence rate and a large number of experimental channels, including a certain number of large-size channels.
Reference 1 (invention patent: high thermal neutron fluence core, patent No. 201210183206.3) discloses a high thermal neutron fluence core comprising fuel assemblies, control rod assemblies and beryllium assemblies; the fuel assemblies are hexagonal sleeve type fuel assemblies, a plurality of fuel assemblies are arranged in an annular compact mode, and a thermal neutron trap is formed on the inner side of an annular region of each fuel assembly; a plurality of hexagonal beryllium components are arranged close to the outer side of the annular region of the fuel component to form an inverted neutron trap; the control rod assemblies are arranged between the fuel assemblies in two rows and two columns at intervals in a shape of Chinese character 'jing'. The reactor core with high thermal neutron fluence rate is beneficial to improving the thermal neutron fluence rate in the irradiation channel, enhancing and widening the irradiation capability and application range of the test reactor on the premise of ensuring safety and feasible structure.
Reference 2 (invention patent: high fast neutron fluence core, patent No. 201210182828.4) discloses a high fast neutron fluence core comprising fuel assemblies, control rod assemblies and beryllium assemblies; the fuel assemblies are hexagonal sleeve type fuel assemblies, a plurality of fuel assemblies are arranged in an annular compact mode, 6 fuel assemblies are arranged on the innermost ring, and a fast neutron trap is formed in the center of the annular area of the fuel assemblies; a plurality of hexagonal beryllium components are arranged close to the outer side of the annular region of the fuel component to form an inverted neutron trap; the control rod assemblies are arranged between the fuel assemblies in two rows and two columns at intervals in a shape of Chinese character 'jing'. The reactor core with high fast neutron fluence meets the international limited U-235 enrichment level and the domestic requirements of fuel core manufacturing and coolant flow rate design level, can obtain higher fast neutron fluence level in an irradiation channel, and enhances and widens the irradiation capability and application range of a test reactor.
The reference 1 and the reference 2 respectively disclose a high-heat and high-fast neutron fluence rate core, wherein fuel assemblies of the core all adopt hexagonal casing type fuel assemblies, and the core comprises core components such as the fuel assemblies, control rod assemblies, beryllium assemblies and the like. In addition to the above components, the cobalt target assemblies are also applied to the above core respectively, and are mainly used for suppressing the neutron fluence rate of the fuel region at the periphery of the core to improve the neutron fluence rate of the fuel region at the center of the core, and are also used for flattening the power distribution of the core and suppressing the residual reactivity of the core, which are important components in the core.
Disclosure of Invention
The invention aims to provide a core design checking core of a hexagonal casing type fuel core cobalt target assembly, so as to meet the requirement of a checking nuclear design program on the calculation reliability of the cobalt target assembly.
In addition, the invention also relates to a test method for inspecting the reactor core.
The invention is realized by the following technical scheme:
the core comprises a fuel assembly, a beryllium assembly, a control rod assembly, a cobalt target assembly and water grid elements, wherein the fuel assembly is a hexagonal sleeve type fuel assembly, the beryllium assembly is a hexagonal beryllium assembly, the control rod assembly consists of a cylindrical control rod and an outer hexagonal inner circular guide pipe, the cobalt target assembly is a hexagonal cobalt target assembly, the water grid elements are hexagonal water grid elements, the core is totally arranged at 265 positions which are respectively 20 boxes of fuel assemblies, 43 boxes of beryllium assemblies, 4 boxes of cobalt target assemblies, 12 control rod assemblies and 186 water grid elements, the 20 boxes of fuel assemblies are intensively arranged in the central area of the core with L12 as the central position, the 43 boxes of beryllium assemblies are arranged at the inner side and the outer side of the fuel assemblies around the fuel assemblies, and the 12 control rod assemblies are arranged between the beryllium assemblies and the fuel assemblies at intervals, the 4-box cobalt target assembly was placed around the fuel assembly next to the fuel assembly, with each fuel assembly, beryllium assembly, control rod assembly, cobalt target assembly, and water grid element occupying 1 position.
The hexagonal sleeve type fuel reactor core cobalt target assembly nuclear design reliability inspection reactor core has the safety rod value of more than 1000pcm, and meets the requirement of the critical safety of the tested reactor core on the safety rod value. According to the invention, the core is tested according to the core design reliability of the hexagonal casing type fuel core cobalt target assembly, a critical physical test is carried out, and the accuracy and reliability of the nuclear design program for computing the cobalt target assembly can be effectively tested. By comparing the actually measured value of the critical physical test with the calculated value of the nuclear design program, whether the cobalt target assembly calculation model needs to be adjusted can be judged; if the measured value and the calculated value have a deviation, the cobalt target assembly calculation model needs to be adjusted to ensure that the adjusted nuclear design program calculated value is consistent with the measured value of the critical test.
Further, 20 cartridges of fuel assemblies are disposed at positions I10, I11, J10, J12, K9, K10, K13, K14, L9, L11, L13, L15, M10, M11, M14, M15, N12, N14, P13, P14, respectively.
Further, 43-box beryllium assemblies are respectively arranged at H7, H8, H9, H10, H11, H12, H13, I7, I8, I13, I14, J8, J14, K7, K8, K11, K12, K15, K16, L7, L8, L12, L16, L17, M8, M9, M12, M13, M16, M17, N10, N16, P10, P11, P16, P17, Q11, Q12, Q13, Q14, Q15, Q16, Q17 positions.
Further, 4-box cobalt target assemblies were disposed at positions I9, I12, P12, P15, respectively.
Further, the 12 control rod assemblies are composed of 4A rod group safety rods, 2B rod group compensation rods, 2C rod group compensation rods, 2D rod group compensation rods and 2E rod group adjusting rods, the 4A rod group safety rods are respectively arranged at J9, J13, N11 and N15 positions, the 2B rod group compensation rods are respectively arranged at J11 and N13 positions, the 2C rod group compensation rods are respectively arranged at L10 and L14 positions, the 2D rod group compensation rods are respectively arranged at J7 and N17 positions, and the 2E rod group adjusting rods are respectively arranged at J15 and N9 positions.
A testing method for testing a core as described above, comprising the steps of:
1) sequentially extracting the control rods according to the following sequence until the reactor core reaches a critical state: firstly, lifting the safety rods of the rod group A from the bottom of the reactor core to the top of the reactor core, then lifting the adjusting rods of the rod group E from the bottom of the reactor core to the half height of the reactor core, and then sequentially lifting the compensating rods of the rod group D, the compensating rods of the rod group C and the compensating rods of the rod group B from the bottom of the reactor core to the top of the reactor core;
2) comparing the actually measured critical rod position with the critical rod position obtained by utilizing the core design program to predict and calculate, wherein if the actually measured critical rod position is consistent with the calculated critical rod position, the core design program is used for accurately and reliably calculating the cobalt target assembly without adjusting a cobalt target assembly calculation model; if the actually measured critical rod position is inconsistent with the calculated critical rod position, the calculation precision of the cobalt target assembly by the nuclear design program does not meet the design requirement, and the calculation model of the nuclear design program needs to be adjusted.
Compared with the prior art, the invention has the following advantages and beneficial effects:
according to the invention, the core is tested according to the core design reliability of the hexagonal casing type fuel core cobalt target assembly, a critical physical test is carried out, and the accuracy and reliability of the nuclear design program for computing the cobalt target assembly can be effectively tested. By comparing the actually measured value of the critical physical test with the calculated value of the nuclear design program, whether the cobalt target assembly calculation model needs to be adjusted can be judged; if the measured value and the calculated value have a deviation, the cobalt target assembly calculation model needs to be adjusted to ensure that the adjusted nuclear design program calculated value is consistent with the measured value of the critical test.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is a schematic diagram of a hexagonal thimble type fuel core cobalt target assembly core design reliability verification core arrangement;
FIG. 2 is a schematic diagram of a hexagonal thimble type fuel core cobalt target assembly nuclear design reliability verification core control rod arrangement.
Reference numbers and corresponding part names in the drawings:
31-fuel assembly, 32-beryllium assembly, 33-control rod assembly, 34-cobalt target assembly, 35-water grid element, 36-A rod group safety rod, 37-B rod group compensation rod, 38-C rod group compensation rod, 39-D rod group compensation rod and 310-E rod group adjusting rod.
Wherein the remaining number designations in figure 1 indicate the core locations.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Example (b):
as shown in fig. 1 and 2, the invention relates to a hexagonal thimble type fuel core cobalt target assembly nuclear design inspection core and a method thereof, wherein the inspection core comprises a fuel assembly 31, a beryllium assembly 32, a control rod assembly 33, a cobalt target assembly 34 and a water grid element 35. The fuel assembly 31 is a hexagonal sleeve type fuel assembly, the beryllium assembly 32 is a hexagonal beryllium assembly, the control rod assembly 33 is composed of a cylindrical control rod and an outer hexagonal inner circular guide pipe, the cobalt target assembly 34 is a hexagonal cobalt target assembly, and the water grid element 35 is a hexagonal water grid element. 265 hexagonal cell positions are arranged in the reactor core. The hexagonal thimble type fuel assemblies 31 are loaded in 20 cases in the core, and are intensively arranged in the central region of the core with the L12 as the center, and are respectively arranged at the positions of I10, I11, J10, J12, K9, K10, K13, K14, L9, L11, L13, L15, M10, M11, M14, M15, N12, N14, P13 and P14. The reactor core is loaded with 43 boxes of beryllium assemblies 32, arranged inside and outside the fuel assemblies 31 and respectively arranged at the positions of H7, H8, H9, H10, H11, H12, H13, I7, I8, I13, I14, J8, J14, K7, K8, K11, K12, K15, K16, L7, L8, L12, L16, L17, M8, M9, M12, M13, M16, M17, N10, N16, P10, P11, P16, P17, Q11, Q12, Q13, Q14, Q15, Q16 and Q17. 12 control rod assemblies 33 are arranged in the core, are arranged between the beryllium assembly 32 and the fuel assembly 31 and are respectively arranged at the positions of J7, J9, J11, J13, J15, L10, L14, N9, N11, N13, N15 and N17, 4 boxes of cobalt target assemblies 34 are loaded in the core, are arranged on the periphery of the fuel assembly 31 next to the fuel assembly 31 and are respectively arranged at the positions of I9, I12, P12 and P15. Except that the fuel assembly 31, the beryllium assembly 32, the cobalt target assembly 34 and the control rod assembly 33 respectively occupy one position in the reactor core, the rest positions are all provided with water grid elements 35, and the whole reactor core is provided with 186 water grid elements 35.
As shown in fig. 2, 12 control rod assemblies 33 including an a rod group safety rod 36, a B rod group compensation rod 37, a C rod group compensation rod 38, a D rod group compensation rod 39 and an E rod group adjustment rod 310 are arranged in the cobalt target assembly nuclear design inspection core for the hexagonal thimble type fuel core according to the invention. The A rod group has 4 safety rods 36 which are arranged at the positions of J9, J13, N11 and N15; 2 compensating rods 37 in the B rod group are arranged at the positions of J11 and N13; 2 compensating rods 38 in the C rod group are arranged at the positions of L10 and L14; 2 compensating rods 39 of the D rod group are arranged at the positions of J7 and N17; the E rod group adjusting rods 310 are 2 in number and are arranged at the positions of J15 and N9.
The control rods are arranged in the core design and inspection core for the cobalt target assembly of the hexagonal sleeve type fuel core as shown in figure 1 and in the control rods of the core design and inspection core for the cobalt target assembly of the hexagonal sleeve type fuel core as shown in figure 2, the cold-state reactivity value of the safety rods 36 of the group A is 10999pcm and is more than 1000pcm, and the requirement of the critical safety of the core to the value of the safety rods is met.
The core arrangement has a calculated value of 1.1352 for the effective multiplication factor nuclear design program in the state that the control rods are all inserted into the core, and a calculated value of 0.8026 for the effective multiplication factor nuclear design program in the state that the control rods are all inserted into the core. According to the rod lifting procedure, firstly, the A rod group safety rods 36 are lifted from the bottom of the reactor core to the top of the reactor core, then the E rod group adjusting rods 310 are lifted from the bottom of the reactor core to the half height of the reactor core, then the D rod group compensating rods 39, the C rod group compensating rods 38 and the B rod group compensating rods 37 are lifted from the bottom of the reactor core to the top of the reactor core in sequence, and the critical rod positions (obtained by using the nuclear design procedure to predict the critical rod positions) are calculated to be 36100.00 cm for the A rod group safety rods, 370.00 cm for the B rod group compensating rods, 3844.94 cm for the C rod group compensating rods, 39100.00 cm for the D rod group compensating rods and 31050.00 cm for the E rod group adjusting rods. And carrying out a critical physical test according to the reactor core arrangement and the rod lifting program to obtain the actually measured critical rod position of the reactor core. Comparing the actually measured critical rod position with the calculated critical rod position, and if the actually measured critical rod position is consistent with the calculated critical rod position, indicating that the calculation of the cobalt target assembly 34 by the kernel design program is accurate and reliable, and the calculation model of the cobalt target assembly 34 does not need to be adjusted; if the actual measurement critical rod position is not consistent with the calculation critical rod position, it indicates that the calculation precision of the core design program for the cobalt target assembly 34 does not meet the design requirement, and the calculation model of the core design program needs to be adjusted.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (6)
1. The core is characterized by comprising a fuel assembly (31), a beryllium assembly (32), a control rod assembly (33), a cobalt target assembly (34) and water grid elements (35), wherein the fuel assembly (31) is a hexagonal sleeve type fuel assembly, the beryllium assembly (32) is a hexagonal beryllium assembly, the control rod assembly (33) consists of a cylindrical control rod and an outer hexagonal inner circular guide pipe, the cobalt target assembly (34) is a hexagonal cobalt target assembly, the water grid elements (35) are hexagonal water grid elements, the core is arranged at 265 positions which are respectively a central area of the core with L12 as a central position, the cobalt target assembly (34) is a hexagonal cobalt target assembly, the water grid elements (35) are hexagonal water grid elements, the core is arranged at 265 positions, the 43 boxes of beryllium assemblies (32) are arranged on the inner side and the outer side of the fuel assembly (31) around the fuel assembly (31), 12 control rod assemblies (33) are arranged between the beryllium assemblies (32) and the fuel assembly (31) at intervals, the 4 boxes of cobalt target assemblies (34) are arranged on the periphery of the fuel assembly (31) next to the fuel assembly (31), and each fuel assembly (31), the beryllium assemblies (32), the control rod assemblies (33), the cobalt target assemblies (34) and the water grid elements (35) respectively occupy 1 position; numbering 265 positions, wherein the numbering rule is as follows:
the reactor core, the fuel assembly (31), the beryllium assembly (32), the control rod assembly (33), the cobalt target assembly (34) and the water grid element (35) are all of a regular hexagon structure, each row between one group of opposite sides of the reactor core is C, D, E, F, G, H, I, J, K, M, N, P, Q, R, S, T, U, V, W in sequence, each row between the other group of opposite sides of the reactor core is 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13, 14, 15, 16, 17, 18, 19, 20 and 21 in sequence, wherein one side with the number of C is adjacent to one side with the number of 3, and one side with the number of W is adjacent to one side with the number of 21.
2. The hexagonal thimble type fuel core cobalt target assembly nuclear design inspection core of claim 1, characterized in that the 20 fuel assemblies (31) are respectively arranged at I10, I11, J10, J12, K9, K10, K13, K14, L9, L11, L13, L15, M10, M11, M14, M15, N12, N14, P13, P14.
3. The hexagonal thimble-type fuel core cobalt target assembly nuclear design inspection core according to claim 1, wherein the 43-box beryllium assemblies (32) are respectively arranged at positions of H7, H8, H9, H10, H11, H12, H13, I7, I8, I13, I14, J8, J14, K7, L7, M7, N7, P7, Q7, and Q7.
4. The hexagonal thimble type fuel core cobalt target assembly nuclear design inspection core of claim 1, characterized in that the 4-box cobalt target assemblies (34) are arranged at I9, I12, P12, P15 positions, respectively.
5. The hexagonal thimble type fuel core cobalt target assembly nuclear design inspection core of claim 1, wherein the 12 control rod assemblies (33) are composed of 4 a rod group safety rods (36), 2B rod group compensation rods (37), 2C rod group compensation rods (38), 2D rod group compensation rods (39), and 2E rod group adjustment rods (310), the 4 a rod group safety rods (36) are respectively disposed at J9, J13, N11, and N15 positions, the 2B rod group compensation rods (37) are respectively disposed at J11 and N13 positions, the 2C rod group compensation rods (38) are respectively disposed at L10 and L14 positions, the 2D rod group compensation rods (39) are respectively disposed at J7 and N17 positions, and the 2E rod group adjustment rods (310) are respectively disposed at J15 and N9 positions.
6. A testing method for inspecting a core according to claim 5, comprising the steps of:
1) sequentially extracting the control rods according to the following sequence until the reactor core reaches a critical state: firstly, lifting the A rod group safety rods (36) to the top of the reactor core from the bottom of the reactor core, then lifting the E rod group adjusting rods (310) to the half height of the reactor core from the bottom of the reactor core, and then sequentially lifting the D rod group compensating rods (39), the C rod group compensating rods (38) and the B rod group compensating rods (37) to the top of the reactor core from the bottom of the reactor core;
2) comparing the actually measured critical rod position with the critical rod position obtained by utilizing the core design program to predict and calculate, wherein if the actually measured critical rod position is consistent with the calculated critical rod position, the core design program is used for accurately and reliably calculating the cobalt target assembly (34) without adjusting a calculation model of the cobalt target assembly (34); if the actual measurement critical rod position is inconsistent with the calculation critical rod position, the calculation precision of the core design program on the cobalt target assembly (34) does not meet the design requirement, and the calculation model of the core design program needs to be adjusted.
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| CN110427706B (en) * | 2019-08-05 | 2022-02-11 | 中国核动力研究设计院 | Method for calculating critical rod position of search reactor core by dynamically increasing fitting order |
| CN111477355B (en) * | 2020-04-16 | 2022-07-01 | 中国原子能科学研究院 | Reactor core fuel assembly and arrangement method thereof, micro neutron source reactor and reactor core thereof |
| CN112366013B (en) * | 2020-11-10 | 2022-04-15 | 中国核动力研究设计院 | Nuclear test method suitable for heat pipe reactor |
| CN114446497B (en) * | 2022-02-17 | 2024-04-19 | 中国核动力研究设计院 | Ultra-high flux reactor core based on square fuel assembly |
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| JPH0255993A (en) * | 1988-08-23 | 1990-02-26 | Hitachi Ltd | Fast breeder |
| JP2668646B2 (en) * | 1993-11-17 | 1997-10-27 | 動力炉・核燃料開発事業団 | Fast reactor core |
| JP2923269B2 (en) * | 1997-09-24 | 1999-07-26 | 核燃料サイクル開発機構 | Core of fast breeder reactor |
| KR100851870B1 (en) * | 2006-10-16 | 2008-08-13 | 한국원자력연구원 | Liquid-Metal-Cooled Fast Reactor Core comprising Nuclear Fuel Assembly with Nuclear Fuel Rods with Varying Fuel Cladding Thickness in each of the Reactor Core Regions |
| CN101447238B (en) * | 2007-11-27 | 2013-03-20 | 中国核动力研究设计院 | Nuclear reactor core capable of improving neutron flux rate |
| CN101719384B (en) * | 2009-12-03 | 2011-12-14 | 中国核动力研究设计院 | Reactor core of nuclear reactor with fast neutron converting area |
| CN103474099B (en) * | 2012-06-06 | 2016-08-03 | 中国核动力研究设计院 | high thermal neutron fluence rate reactor core |
| CN103474097B (en) * | 2012-06-06 | 2016-08-10 | 中国核动力研究设计院 | High Fast neutron flux reactor core |
| JP6753760B2 (en) * | 2016-10-25 | 2020-09-09 | 日立Ｇｅニュークリア・エナジー株式会社 | Fast reactor core |
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