CN109215811B - Hexagonal beryllium assembly and aluminum assembly nuclear design reliability inspection reactor core and adjusting method - Google Patents
Hexagonal beryllium assembly and aluminum assembly nuclear design reliability inspection reactor core and adjusting method Download PDFInfo
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- CN109215811B CN109215811B CN201811069729.9A CN201811069729A CN109215811B CN 109215811 B CN109215811 B CN 109215811B CN 201811069729 A CN201811069729 A CN 201811069729A CN 109215811 B CN109215811 B CN 109215811B
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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
- G21C5/06—Means for locating or supporting fuel elements
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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
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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
- G21C5/14—Moderator or core structure; Selection of materials for use as moderator characterised by shape
- G21C5/16—Shape of its constituent parts
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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
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- 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 beryllium assembly and aluminum assembly nuclear design reliability checking reactor core and an adjusting method thereof, wherein the hexagonal beryllium assembly and aluminum assembly nuclear design reliability checking reactor core comprises a fuel assembly, a control rod assembly, a water grid element, a beryllium assembly and an aluminum assembly, the control rod assembly consists of a cylindrical control rod and an outer hexagonal and inner circular guide tube, the aluminum assembly is a hexagonal aluminum assembly, the beryllium components are hexagonal beryllium components, the core is totally arranged at 265 positions, namely 11 boxes of fuel components, 12 control rod components, 16 boxes of beryllium components, 72 boxes of aluminum components and 154 water grid cells, the 11 boxes of fuel components are intensively arranged in the central area of the core with L12 as the center, the 16 boxes of beryllium components are arranged around the fuel components, the 72 boxes of aluminum components are arranged around the 16 boxes of beryllium components, and the 12 control rod components are arranged around the beryllium components at intervals among the aluminum components. The invention can meet the requirement of a nuclear design program on the calculation reliability of the hexagonal sleeve type fuel beryllium assembly and the aluminum assembly.
Description
Technical Field
The invention relates to the technical field of nuclear reactor design, in particular to a hexagonal beryllium assembly and aluminum assembly nuclear design reliability inspection reactor core and an adjusting 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 disclosed in references 1 and 2, an aluminum component is used as a component commonly used in a test reactor, and may be applied to the above core as an important component. Therefore, it is necessary to perform critical physical tests on the hexagonal sleeve type fuel assembly core containing the beryllium assembly and the aluminum assembly to check the calculation accuracy and reliability of the core design program on the hexagonal beryllium assembly and the aluminum assembly.
Disclosure of Invention
The invention aims to provide a core for verifying the nuclear design reliability of hexagonal beryllium components and aluminum components so as to meet the requirement of a nuclear design program on the calculation reliability of the hexagonal beryllium components and the aluminum components.
The present invention also relates to a method for adjusting the inspection core.
The invention is realized by the following technical scheme:
the core comprises a fuel assembly, a control rod assembly, water grid elements, beryllium assemblies and aluminum assemblies, wherein the fuel assembly is a hexagonal sleeve type fuel assembly, the control rod assembly consists of a cylindrical control rod and an outer hexagonal inner circular guide pipe, the water grid elements are hexagonal water grid elements, the aluminum assembly is a hexagonal aluminum assembly, the beryllium assemblies are hexagonal beryllium assemblies, the core is totally arranged at 265 positions which are respectively 11 boxes of fuel assemblies, 12 control rod assemblies, 16 boxes of beryllium assemblies, 72 boxes of aluminum assemblies and 154 water grid elements, the 11 boxes of fuel assemblies are intensively arranged in the central area of the core with L12 as the central position, the 16 boxes of beryllium assemblies are arranged around the fuel assembly, the 72 boxes of aluminum assemblies are arranged around the 16 boxes of beryllium assemblies, the 12 control rod assemblies are arranged around the beryllium assemblies at intervals among the aluminum assemblies, each fuel assembly, control rod assembly, beryllium assembly, aluminum assembly and water grid element occupy 1 position.
The hexagonal beryllium assembly and aluminum assembly nuclear design reliability inspection reactor core has the safety rod value of more than 1000pcm, and meets the requirement of critical safety of the reactor core under test on the safety rod value. According to the invention, the reliability checking reactor core is designed according to the hexagonal beryllium assembly and the aluminum assembly core, the critical physical test is carried out, and the calculation precision and reliability of the nuclear design program on the hexagonal beryllium assembly and the aluminum assembly can be effectively checked. Comparing the actually measured value of the critical physical test with the calculated value of the nuclear design program, judging whether the beryllium assembly and the aluminum assembly calculation model need to be adjusted; if the actual measured value and the calculated value have deviation, the beryllium component and the aluminum component calculation model need to be adjusted to ensure that the adjusted nuclear design program calculated value is consistent with the actual measured value of the critical test.
Further, 11-cartridge fuel assemblies were disposed at positions K10, K11, K12, K13, L11, L12, L13, M11, M12, M13, M14, respectively.
Further, 16-box beryllium assemblies are arranged at positions J9, J10, J11, J12, J13, K9, K14, L10, L14, M10, M15, N11, N12, N13, N14, N15, respectively.
Further, the 72-box aluminum components are respectively arranged at positions of G6, G7, G8, G9, G10, G11, G12, G13, H6, H7, H8, H10, H12, H13, H14, I6, I7, I9, I10, I11, I12, I14, I15, J6, J7, J8, J14, J15, K15, L15, M15, N15, P15.
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 positions I8, I13, P11 and P16, the 2B rod group compensation rods are respectively arranged at positions H9 and Q15, the 2C rod group compensation rods are respectively arranged at positions H11 and Q13, the 2D rod group compensation rods are respectively arranged at positions K15 and M9, and the 2E rod group adjusting rods are respectively arranged at positions K8 and M16.
An adjustment method for inspecting a reactor core is used for respectively obtaining a calculated value and an actual value of an effective multiplication coefficient of the reactor core:
if the deviation between the measured value and the calculated value of the effective multiplication coefficient of the reactor core is less than 0.2% under the state that the control rod assemblies all put forward the reactor core, the nuclear design program can accurately and reliably calculate the beryllium assembly and the aluminum assembly without adjusting calculation models of the beryllium assembly and the aluminum assembly;
if the deviation between the measured value and the calculated value of the effective multiplication coefficient of the reactor core under the state that all the control rod assemblies put forward the reactor core is more than 0.2%, the calculation precision of the nuclear design program on the beryllium assembly and the aluminum assembly does not meet the design requirement, and the beryllium assembly and the aluminum assembly calculation model need to be adjusted to ensure that the calculated value of the adjusted nuclear design program is consistent with the measured value of the critical test.
Further, when the calculated effective core multiplication coefficient is smaller than the actual value and the deviation is larger than 0.2%, the effective core multiplication coefficient is reduced by exchanging the positions of the aluminum assembly at I12 and the beryllium assembly at J13.
Further, when the calculated value of the effective multiplication coefficient of the reactor core is smaller than the actual value and the deviation is still larger than 0.2% after the adjustment, the effective multiplication coefficient of the experimental reactor core is reduced by arranging the beryllium assemblies in an evacuating way or inserting part of the control rod assemblies into the reactor core.
Further, when the calculated value of the effective core multiplication coefficient is larger than the measured value and the deviation is larger than 0.2%, the aluminum assemblies at the positions of H10, L8, L16 and Q14 are replaced by water grid cells, so that the effective core multiplication coefficient of the test core is improved.
Further, when the calculated value of the effective multiplication coefficient of the reactor core is larger than the measured value and the deviation is still larger than 0.2% after the adjustment, the effective multiplication coefficient of the experimental reactor core is improved by adding beryllium assemblies into the reactor core.
Specifically, the core arrangement has a core effective multiplication factor nuclear design program calculated value of 1 in a state where all control rods are present in the core. Carrying out a critical physical test according to the reactor core arrangement, and if the actually measured effective multiplication coefficient of the reactor core is equal to a nominal value 1 (the deviation from 1 is less than 0.2%) under the state that the control rods are all put out of the reactor core, the nuclear design program can accurately and reliably calculate the beryllium component and the aluminum component without adjusting calculation models of the beryllium component and the aluminum component; if the actual measurement effective multiplication coefficient of the reactor core under the state that the control rods are all put forward the reactor core is not equal to the nominal value 1 (the deviation from 1 is more than 0.2%), the calculation precision of the nuclear design program on the beryllium assembly and the aluminum assembly does not meet the design requirement, and the calculation model of the beryllium assembly and the aluminum assembly needs to be adjusted to ensure that the calculation value of the adjusted nuclear design program is consistent with the actual measurement value of the critical test.
The positions of beryllium components and aluminum components in the reactor core can be adjusted according to the actual measurement result of the critical test, and when the actual measurement effective multiplication coefficient of the reactor core critical test is larger than 1 (namely the deviation between the calculated value of the nuclear design program and the critical test result is larger than 0.2 percent and the calculated value of the effective multiplication coefficient is smaller) in the state that the control rods are all put out of the reactor core, the aluminum components at the position I12 and the beryllium components at the position J13 are interchanged, so that the effective multiplication coefficient of the reactor core can be reduced, and the requirement of the critical test of the reactor core can be met. If the calculated deviation is outside the above adjustment range, other measures are taken to make the core critical, such as, for example, the beryllium assembly being deployed in a sparse manner or the control rods being partially inserted into the core.
The positions of beryllium components and aluminum components in the reactor core can be adjusted according to the actual measurement result of the critical test, and when the actual measurement effective multiplication coefficient of the reactor core critical test is smaller than 1 (namely the deviation between the calculated value of the nuclear design program and the critical test result is larger than 0.2 percent and the calculated value of the effective multiplication coefficient is larger) in the state that the control rods are all put out of the reactor core, the aluminum components at the positions of H10, L8, L16 and Q14 are replaced by water grid elements, so that the effective multiplication coefficient of the reactor core under the test can be improved, and the requirement of the reactor core critical test can be met. If the calculated deviation is outside the above adjustment range, other measures are taken to make the core critical, for example, adding more boxes of beryllium components to the core.
Compared with the prior art, the invention has the following advantages and beneficial effects:
1. according to the invention, the reliability checking reactor core is designed according to the hexagonal beryllium assembly and the aluminum assembly core, the critical physical test is carried out, and the calculation precision and reliability of the nuclear design program on the hexagonal beryllium assembly and the aluminum assembly can be effectively checked.
2. The invention discloses a core for verifying the nuclear design reliability of hexagonal beryllium components and aluminum components, and provides a core arrangement adjusting method when a critical physical test measured value and a nuclear design program calculated value have a deviation so as to ensure that the core meets the critical test requirement.
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 beryllium assembly and aluminum assembly core design reliability inspection core layout;
FIG. 2 is a schematic diagram of a hexagonal beryllium assembly and aluminum assembly core design reliability check core control rod arrangement.
Reference numbers and corresponding part names in the drawings:
31-fuel assembly, 32-beryllium assembly, 33-aluminum assembly, 34-control rod 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 the drawings indicate the locations of the cores.
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 beryllium assembly and aluminum assembly core design reliability inspection core and an adjustment method, wherein the inspection core comprises a fuel assembly 31, a beryllium assembly 32, an aluminum assembly 33, a control rod 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 aluminum assembly 33 is a hexagonal aluminum assembly, the control rod assembly 34 consists of a cylindrical control rod and an outer hexagonal inner circular guide tube, and the water grid element 35 is a hexagonal water grid element. The core is arranged in 265 hexagonal cell positions, and each fuel assembly 31, beryllium assembly 32, aluminum assembly 33, control rod assembly 34 and water cell 35 occupies 1 position. The fuel assemblies 31 are loaded in 11 cassettes in the core, and are collectively arranged in the central region of the core centered on L12, and are arranged at positions K10, K11, K12, K13, L11, L12, L13, M11, M12, M13, and M14, respectively. The reactor core is loaded with 16 boxes of beryllium assemblies 32, and the beryllium assemblies 32 are arranged around the fuel assemblies 31 and are respectively arranged at the positions of J9, J10, J11, J12, J13, K9, K14, L10, L14, M10, M15, N11, N12, N13, N14 and N15. The core is loaded with 72 boxes of aluminum assemblies 33, the aluminum assemblies are arranged around the beryllium assembly 32 and are respectively arranged at positions of G6, G7, G8, G9, G10, G11, G12, G13, H6, H7, H8, H10, H12, H13, H14, I6, I7, I9, I10, I11, I12, I14, I15, J6, J7, J8, J14, J15, K15, L15, M15, N15, P15, R15, P15, and P15. 12 control rod assemblies 34 are arranged in the core, are arranged among the aluminum assemblies 33 at intervals around the beryllium assemblies 32 and are respectively arranged at the positions of H9, H11, I8, I13, K8, K15, M9, M16, P11, P16, Q13 and Q15. Except the grid cell positions occupied by the fuel group 31, the beryllium component 32, the aluminum component 33 and the control rod component 34, water grid cells 35 are arranged at the rest positions in the reactor core, and 154 water grid cells 35 are arranged in the whole reactor core.
As shown in fig. 2, 12 control rod assemblies, including an a-group safety rod 36, a B-group compensation rod 37, a C-group compensation rod 38, a D-group compensation rod 39, and an E-group adjustment rod 310, are arranged in the hexagonal thimble type fuel core aluminum assembly nuclear design reliability check core according to the present invention. The A rod group has 4 safety rods 36 which are arranged at positions I8, I13, P11 and P16; 2 compensating rods 37 in the B rod group are arranged at the positions of H9 and Q15; 2 compensating rods 38 in the C rod group are arranged at the positions of H11 and Q13; 2 compensating rods 39 of the D rod group are arranged at the positions of K15 and M9; the E rod group adjusting rods 310 are 2 in number and are arranged at the positions of K8 and M16.
As shown in figure 1, the hexagonal beryllium assembly and aluminum assembly nuclear design reliability checking reactor core and as shown in figure 2, the hexagonal beryllium assembly 32 and aluminum assembly 33 nuclear design reliability checking reactor core control rod arrangement, the cold-state reactivity value of the safety rod of the A rod group is 1161pcm and is more than 1000pcm, and the requirement of the critical safety of the reactor core to the value of the safety rod is met.
As shown in FIG. 1, when the hexagonal beryllium assembly 32 and the aluminum assembly 33 are used for designing the nuclear reliability checking core, under the condition that the control rods are all put into the core, the calculated value of the effective multiplication coefficient nuclear design program of the core is 1.0015, and the deviation from the nominal value 1 is less than 0.2%, namely the core is considered to be just critical. Carrying out a critical physical test according to the core arrangement, and if the actually measured effective multiplication coefficient of the core is equal to a nominal value 1 (the deviation from 1 is less than 0.2%) under the state that the control rod assemblies 34 all propose the core, the nuclear design program can accurately and reliably calculate the beryllium assembly 32 and the aluminum assembly 33 without adjusting calculation models of the beryllium assembly 32 and the aluminum assembly 33; if the actual measurement effective multiplication coefficient of the reactor core under the state that the control rod assembly 34 completely proposes the reactor core is not equal to the nominal value 1 (the deviation from 1 is more than 0.2%), the calculation precision of the beryllium assembly 32 and the aluminum assembly 34 by the nuclear design program does not meet the design requirement, and the calculation value of the nuclear design program can be ensured to be consistent with the actual measurement value of the critical test by adjusting the calculation models of the beryllium assembly 32 and the aluminum assembly 34.
When the actual effective multiplication coefficient is larger than 1 (namely the deviation between the calculated value of the nuclear design program and the result of the critical test is larger than 0.2%, and the calculated value of the effective multiplication coefficient is smaller) in the critical test of the reactor core shown in fig. 1, the aluminum assembly 33 at the position I12 and the beryllium assembly 32 at the position J13 can be interchanged, the calculated value of the effective multiplication coefficient of the reactor core to 0.9976, and the requirement of the critical test of the reactor core is met. If the calculated deviation is outside the above adjustment range, other measures are taken to make the core critical, such as, for example, the beryllium assemblies 32 being arranged in a sparse manner or portions of the control rod assemblies 34 being inserted into the core.
When the actual effective multiplication coefficient of the reactor core in the critical test shown in fig. 1 is smaller than 1 (namely, the deviation between the calculated value of the nuclear design program and the result of the critical test is larger than 0.2%, and the calculated value of the effective multiplication coefficient is larger), the aluminum assemblies 33 at the positions of H10, L8, L16 and Q14 can be replaced by the water grid elements 35, so that the calculated value of the effective multiplication coefficient of the reactor core in the test is increased to 1.0057, and the requirement of the critical test of the reactor core is met. If the calculated deviation is outside the above adjustment range, then other measures are taken to make the core critical, such as adding more boxes of beryllium assemblies 32 to the core.
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 (10)
1. The hexagonal beryllium component and aluminum component nuclear design reliability inspection core is characterized by comprising a fuel component (31), a control rod component (34), a water grid element (35), a beryllium component (32) and an aluminum component (33), wherein the fuel component (31) is a hexagonal sleeve type fuel component, the control rod component (34) consists of a cylindrical control rod and an outer hexagonal inner circular guide pipe, the water grid element (35) is a hexagonal water grid element, the aluminum component (33) is a hexagonal aluminum component, the beryllium component (32) is a beryllium hexagonal component, the core is totally arranged at 265 positions which are respectively 11 boxes of fuel components (31), 12 control rod components (34), 16 boxes of beryllium components (32), 72 boxes of aluminum components (33) and 154 water grid elements (35), and the 11 boxes of fuel components (31) are intensively arranged in the central area of the core which takes L12 as the central position, the fuel assembly comprises 16 boxes of beryllium assemblies (32), 72 boxes of aluminum assemblies (33), 12 control rod assemblies (34), a water grid element (35) and fuel assemblies (31), wherein the 16 boxes of beryllium assemblies (32) are arranged around the fuel assemblies (31), the 72 boxes of aluminum assemblies (33) are arranged around the 16 boxes of beryllium assemblies (32), the 12 control rod assemblies (34) are arranged between the aluminum assemblies (33) at intervals around the beryllium assemblies (32), and each fuel assembly (31), control rod assembly (34), beryllium assembly (32), aluminum assembly (33) and water grid element (35) respectively occupy 1 position;
numbering 265 positions, wherein the numbering rule is as follows:
the reactor core, the fuel assembly (31), the control rod assembly (34), the water grid element (35), the beryllium assembly (32) and the aluminum assembly (33) 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 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 V is adjacent to one side with the number of 21.
2. The hexagonal beryllium assembly and aluminum assembly core design reliability verification core of claim 1, wherein the 11 boxes of fuel assemblies (31) are arranged at the K10, K11, K12, K13, L11, L12, L13, M11, M12, M13, M14 positions, respectively.
3. The hexagonal beryllium assembly and aluminum assembly core design reliability verification core of claim 1, wherein the 16 boxes of beryllium assemblies (32) are arranged at J9, J10, J11, J12, J13, K9, K14, L10, L14, M10, M15, N11, N12, N13, N14, N15 positions, respectively.
4. The hexagonal beryllium assembly and aluminum assembly core design reliability inspection core according to claim 1, wherein the 72 cases of aluminum assemblies (33) are respectively arranged at positions G6, G7, G8, G9, G10, G11, G12, G13, H6, H7, H8, H10, H12, H13, H14, I6, I7, I9, I10, I11, I12, I14, I15, J6, J7, J8, J14, J15, K15, L15, M15, N15, N15.
5. The hexagonal beryllium and aluminum component core design reliability verification core according to claim 1, wherein the 12 control rod assemblies (34) 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), wherein the 4 a rod group safety rods (36) are respectively arranged at positions I8, I13, P11, and P16, the 2B rod group compensation rods (37) are respectively arranged at positions H9 and Q15, the 2C rod group compensation rods (38) are respectively arranged at positions H11 and Q13, the 2D rod group compensation rods (39) are respectively arranged at positions K15 and M9, and the 2E rod group adjustment rods (310) are respectively arranged at positions K8 and M16.
6. A method for adjusting a nuclear core according to any one of claims 1 to 5, wherein the calculated and measured values of the effective multiplication factor of the core are obtained by:
if the deviation between the measured value and the calculated value of the effective multiplication coefficient of the reactor core is less than 0.2% under the state that the control rod assemblies (34) are all put out of the reactor core, the nuclear design program can accurately and reliably calculate the beryllium assemblies (32) and the aluminum assemblies (33) without adjusting calculation models of the beryllium assemblies (32) and the aluminum assemblies (33);
if the deviation between the actual measurement value and the calculated value of the effective multiplication coefficient of the reactor core in the reactor core state is larger than 0.2 percent when all the control rod assemblies (34) are put forward, the calculation precision of the nuclear design program on the beryllium assembly (32) and the aluminum assembly (33) does not meet the design requirement, and the calculation models of the beryllium assembly (32) and the aluminum assembly (33) need to be adjusted to ensure that the calculated value of the adjusted nuclear design program is consistent with the actual measurement value of the critical test.
7. The method for conditioning a nuclear core according to claim 6, wherein when the calculated value of the effective multiplication factor of the core is smaller than the actual value and the deviation is greater than 0.2%, the effective multiplication factor of the core under test is reduced by interchanging the positions of the aluminum assembly (33) at I12 and the beryllium assembly (32) at J13.
8. The method for conditioning a nuclear reactor core according to claim 7, wherein when the calculated value of the effective multiplication factor of the nuclear reactor core is smaller than the measured value and the deviation is still greater than 0.2% after the conditioning method according to claim 7, the effective multiplication factor of the test nuclear reactor core is reduced by arranging the beryllium assemblies (32) in a sparse way or inserting part of the control rod assemblies (34) into the nuclear reactor core.
9. The method for adjusting a nuclear reactor core as claimed in claim 6, wherein when the calculated value of the effective multiplication factor of the core is larger than the actually measured value and the deviation is larger than 0.2%, the effective multiplication factor of the core under test is increased by replacing the aluminum assemblies (33) at the positions of H10, L8, L16 and Q14 with the water grid elements (35).
10. The method for adjusting a nuclear reactor core according to claim 9, wherein when the calculated value of the effective multiplication factor of the nuclear reactor core is larger than the measured value and the deviation is still larger than 0.2% after the adjustment according to the adjustment method of claim 9, the effective multiplication factor of the nuclear reactor core under test is increased by adding beryllium assemblies (32) to the nuclear reactor core.
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