CN109215811A - Hexagon beryllium component and aluminium component nuclear design certificate authenticity reactor core and method of adjustment - Google Patents
Hexagon beryllium component and aluminium component nuclear design certificate authenticity reactor core and method of adjustment Download PDFInfo
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- CN109215811A CN109215811A CN201811069729.9A CN201811069729A CN109215811A CN 109215811 A CN109215811 A CN 109215811A CN 201811069729 A CN201811069729 A CN 201811069729A CN 109215811 A CN109215811 A CN 109215811A
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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
- 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 hexagon beryllium component and aluminium component nuclear design certificate authenticity reactor core and methods of adjustment, hexagon beryllium component and aluminium component nuclear design certificate authenticity reactor core include fuel assembly, C&P systems, boom member, beryllium component and aluminium component, the C&P systems are made of cylinder control bar and outer-hexagonal inner circular guide pipe, the aluminium component hexagon aluminium component, the beryllium component is hexagon beryllium component, the reactor core arranges 265 positions altogether, respectively 11 box fuel assemblies, 12 C&P systems, 16 box beryllium components, 72 box aluminium components and 154 boom members, 11 box fuel assembly centralized arrangements are using L12 as the middle section of the reactor core of center position, 16 box beryllium components are arranged around fuel assembly, 72 box aluminium components are arranged around 16 box beryllium components, 12 C&P systems enclose Around beryllium inter-module every being arranged between aluminium component.The present invention can examine demand of the nuclear design program to hexagon thimble tube fuel beryllium component and aluminium Assembly calculation reliability enough.
Description
Technical field
The present invention relates to nuclear reactor designs technical fields, and in particular to hexagon beryllium component and aluminium component nuclear design are reliable
Property examine reactor core and method of adjustment.
Background technique
The development of nuclear reactor be unable to do without test reactor, and test reactor has very important work to the exploitation of various reactor heap-type
With.The development trend of advanced test reactor is that have high thermal neutron or Fast neutron flux, the experimental hole more than number, including one
The large scale duct of fixed number amount.
Documents 1 (patent of invention: high fever neutron fluence rate reactor core, the patent No. 201210183206.3) disclose one kind
High fever neutron fluence rate reactor core, the reactor core include fuel assembly, C&P systems and beryllium component；Fuel assembly is hexagon casing
Type fuel assembly, several fuel assemblies compact Layout in a ring form thermal neutron trap in the inside of fuel assembly annular region；
It is closely disposed with several hexagon beryllium components on the outside of fuel assembly annular region, forms neutron sink；Several control rods
Two column are in " well " font arranged for interval between fuel assembly to component in two rows.The high fever neutron fluence rate reactor core, is guaranteeing
Under the premise of safety and structure are feasible, are conducive to improve thermal neutron fluence rate in irradiation channel, enhance and widen the spoke of test reactor
According to ability and application range.
Documents 2 (patent of invention: high Fast neutron flux reactor core, the patent No. 201210182828.4) disclose one kind
High Fast neutron flux reactor core, the reactor core include fuel assembly, C&P systems and beryllium component；Fuel assembly is hexagon casing
Type fuel assembly, several fuel assemblies compact Layout in a ring have 6 fuel assemblies on innermost layer ring, in its annular region
Center at formed fast neutron trap；It is closely disposed with several hexagon beryllium components on the outside of fuel assembly annular region, is formed
Neutron sink；Two column are in " well " font arranged for interval between fuel assembly to several C&P systems in two rows.It is described high fast
Neutron fluence rate reactor core meets the U-235 degree of enrichment of international limitation horizontal and the domestic manufacture of cartridge body and coolant flow speed
The requirement of design level can get Fast neutron flux level in higher irradiation channel, enhance and widen the irradiation of test reactor
Ability and application range.
Documents 1 and documents 2 individually disclose a kind of high fever, high Fast neutron flux reactor core, fuel assembly
It is all made of hexagon thimble tube fuel assembly, reactor core includes the core components such as fuel assembly, C&P systems, beryllium component.Except public affairs
Be distributed in outside the above-mentioned component in documents 1 and documents 2, aluminium component as a kind of component being usually used in test reactor,
It may be applied to above-mentioned reactor core as important component.Therefore, it is necessary to be directed to the hexagon thimble tube of component containing beryllium and aluminium component
Fuel assembly reactor core, carry out critical physical test, by examine Nuclear design program to hexagon beryllium component and aluminium component in terms of
Calculate precision and reliability.
Summary of the invention
The purpose of the present invention is to provide hexagon beryllium components and aluminium component nuclear design certificate authenticity reactor core, to meet
Demand of the nuclear design program to hexagon beryllium component and aluminium Assembly calculation reliability is examined, the reactor core display is opened according to the present invention
Critical physical test is opened up, can effectively examine nuclear design program to hexagon thimble tube fuel assembly in-core beryllium component and aluminium Assembly calculation
Precision and reliability.
Moreover, it relates to the method for adjustment of above-mentioned inspection reactor core.
The present invention is achieved through the following technical solutions:
Hexagon beryllium component and aluminium component nuclear design certificate authenticity reactor core, the reactor core includes fuel assembly, control rod
Component, boom member, beryllium component and aluminium component, the fuel assembly are hexagon thimble tube fuel assembly, the C&P systems
It is made of cylinder control bar and outer-hexagonal inner circular guide pipe, the boom member is hexagon boom member, the aluminium component six
Side shape aluminium component, the beryllium component are hexagon beryllium component, and the reactor core arranges 265 positions, respectively 11 box fuel stacks altogether
Part, 12 C&P systems, 16 box beryllium components, 72 box aluminium components and 154 boom members, 11 box fuel assembly centralized arrangements with
L12 is the middle section of the reactor core of center position, and 16 box beryllium components arrange that 72 box aluminium components surround 16 box berylliums around fuel assembly
Component arrangement, 12 C&P systems around beryllium inter-module every being arranged between aluminium component, each fuel assembly, control rod group
Part, beryllium component, aluminium component and boom member respectively account for 1 position.
Hexagon beryllium component and aluminium component nuclear design certificate authenticity reactor core of the present invention, safety rod value are greater than
1000pcm meets the requirement that test reactor core criticality safety is worth safety rod.The hexagon beryllium component and aluminium according to the present invention
Component nuclear design certificate authenticity reactor core carries out critical physical test, can effectively examine nuclear design program to hexagon beryllium component
With the precision and reliability of aluminium Assembly calculation.Measured value and nuclear design program calculated value are tested by comparison critical physical, can be sentenced
It is disconnected whether to need to be adjusted beryllium component and aluminium Assembly calculation model；If measured value and calculated value are there are deviation, then need to adjust
Beryllium component and aluminium Assembly calculation model, to guarantee that nuclear design program calculated value is consistent with marginal test measured value after adjustment.
Further, 11 box fuel assemblies be arranged in K10, K11, K12, K13, L11, L12, L13, M11, M12,
The position M13, M14.
Further, 16 box beryllium components be arranged in J9, J10, J11, J12, J13, K9, K14, L10, L14, M10,
The position M15, N11, N12, N13, N14, N15.
Further, 72 box aluminium components be arranged in 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、J16、K7、K15、K16、
L6、L7、L8、L9、L15、L16、L17、L18、M7、M8、M17、M18、N8、N9、N10、N16、N17、N18、P10、P12、P13、
P14, P15, P17, P18, Q10, Q11, Q12, Q14, Q16, Q17, Q18, R11, R12, R13, R14, R15, R16, R17, R18
It sets.
Further, 12 C&P systems are by 4 A stick group safety rods, 2 B stick group shim rods, 2 C stick group compensation
Stick, 2 D stick group shim rods, 2 E stick group regulating rod compositions, 4 A stick group safety rods are respectively arranged in I8, I13, P11, P16
It sets, 2 B stick group shim rods are respectively arranged in the position H9, Q15, and 2 C stick group shim rods are respectively arranged in the position H11, Q13, and 2
D stick group shim rod is respectively arranged in the position K15, M9, and 2 E stick group regulating rods are respectively arranged in the position K8, M16.
A kind of method of adjustment for examining reactor core, obtains reactor core effective multiplication factor calculated value and measured value respectively:
If C&P systems all propose reactor core states under reactor core effective multiplication factor measured value and calculated value it is inclined
Difference is less than 0.2%, then nuclear design program is accurate and reliable to beryllium component and aluminium Assembly calculation, does not need to beryllium component and aluminium component meter
Model is calculated to be adjusted；
If C&P systems all propose the measured value of reactor core effective multiplication factor and the deviation of calculated value under reactor core state
Greater than 0.2%, then nuclear design program is unsatisfactory for design requirement to beryllium component and aluminium Assembly calculation precision, need to adjust beryllium component and
Aluminium Assembly calculation model, to guarantee that nuclear design program calculated value is consistent with marginal test measured value after adjustment.
Further, when reactor core effective multiplication factor calculated value be less than measured value, and deviation be greater than 0.2% when, pass through by
The beryllium component transposition at aluminium component and J13 at I12, reduces test reactor core effective multiplication factor.
Further, when reactor core effective multiplication factor calculated value is less than measured value, and deviation is still after above-mentioned adjustment
When greater than 0.2%, by the way that beryllium component is evacuated arrangement or part C&P systems are inserted into reactor core, reduces test reactor core and effectively increase
Grow coefficient.
Further, when reactor core effective multiplication factor calculated value be greater than measured value, and deviation be greater than 0.2% when, pass through by
The aluminium component of the position H10, L8, L16, Q14 replaces with boom member, improves test reactor core effective multiplication factor.
Further, when reactor core effective multiplication factor calculated value is greater than measured value, and deviation is still after above-mentioned adjustment
When greater than 0.2%, by increasing beryllium component to heap in-core, test reactor core effective multiplication factor is improved.
Specifically, the reactor core display, in the case where control rod all proposes reactor core state, reactor core effective multiplication factor nuclear design
Program calculated value is 1.Carry out critical physical test according to the reactor core display, if control rod all proposes reactor core under reactor core state
It surveys effective multiplication factor and is equal to nominal value 1 (and 1 deviation is less than 0.2%), then illustrate nuclear design program to beryllium component and aluminium group
Part calculates accurately and reliably, does not need to be adjusted beryllium component and aluminium Assembly calculation model；If control rod all proposes heap wick-like
Reactor core actual measurement effective multiplication factor then illustrates nuclear design program to beryllium not equal to nominal value 1 (and 1 deviation is greater than 0.2%) under state
Component and aluminium Assembly calculation precision are unsatisfactory for design requirement, need to adjust beryllium component and aluminium Assembly calculation model, to guarantee to adjust
Nuclear design program calculated value is consistent with marginal test measured value afterwards.
Beryllium component and aluminium module position can be adjusted according to marginal test measured result in the reactor core, complete in control rod
Portion proposes under reactor core state, when arrangement reactor core marginal test surveys (nuclear design journey when effective multiplication factor is greater than 1 as previously described
Sequence calculated value and marginal test result error are greater than 0.2%, and effective multiplication factor calculated value is less than normal), by I12 at aluminium component and
Beryllium component transposition at J13 can reduce test reactor core effective multiplication factor, meet the requirement of reactor core marginal test.If calculating
Deviation has exceeded above-mentioned adjusting range, then uses other measures so that reactor core is critical, for example, beryllium component is evacuated arrangement or by portion
Control rod is divided to be inserted into reactor core.
Beryllium component and aluminium module position can be adjusted according to marginal test measured result in the reactor core, complete in control rod
Under portion's proposition reactor core state, (the nuclear design journey when arrangement reactor core marginal test actual measurement effective multiplication factor is less than 1 as previously described
Sequence calculated value and marginal test result error are greater than 0.2%, and effective multiplication factor calculated value is bigger than normal), by H10, L8, L16, Q14
The aluminium component of position replaces with boom member, and test reactor core effective multiplication factor can be improved, and meets the requirement of reactor core marginal test.If meter
It calculates deviation and has exceeded above-mentioned adjusting range, then use other measures so that reactor core is critical, for example, increasing more box berylliums to heap in-core
Component.
Compared with prior art, the present invention having the following advantages and benefits:
1, the hexagon beryllium component and aluminium component nuclear design certificate authenticity reactor core according to the present invention carry out critical physical
Test, can effectively examine nuclear design program to the precision and reliability of hexagon beryllium component and aluminium Assembly calculation.
2, hexagon beryllium component and aluminium component nuclear design certificate authenticity reactor core of the present invention, while giving critical object
Reason test measured value and nuclear design program calculated value have reactor core display method of adjustment when deviation, to guarantee that reactor core meets critical examination
Test requirement.
Detailed description of the invention
Attached drawing described herein is used to provide to further understand the embodiment of the present invention, constitutes one of the application
Point, do not constitute the restriction to the embodiment of the present invention.In the accompanying drawings:
Fig. 1 is hexagon beryllium component and aluminium component nuclear design certificate authenticity reactor core display schematic diagram；
Fig. 2 is hexagon beryllium component and aluminium component nuclear design certificate authenticity reactor core control rod arrangement schematic diagram.
Label and corresponding parts title in attached drawing:
31- fuel assembly, 32- beryllium component, 33- aluminium component, 34- C&P systems, 35- boom member, 36-A stick group safety
Stick, 37-B stick group shim rod, 38-C stick group shim rod, 39-D stick group shim rod, 310-E stick group regulating rod.
Wherein, in attached drawing remaining number designation indicate reactor core position.
Specific embodiment
To make the objectives, technical solutions, and advantages of the present invention clearer, below with reference to embodiment and attached drawing, to this
Invention is described in further detail, and exemplary embodiment of the invention and its explanation for explaining only the invention, are not made
For limitation of the invention.
Embodiment:
As shown in Figure 1 and Figure 2, the present invention relates to hexagon beryllium components and aluminium component nuclear design certificate authenticity reactor core and tune
Adjusting method, the inspection reactor core include fuel assembly 31, beryllium component 32, aluminium component 33, C&P systems 34 and boom member 35.Combustion
Material component 31 is hexagon thimble tube fuel assembly, and beryllium component 32 is hexagon beryllium component, and aluminium component 33 is hexagon aluminium component,
C&P systems 34 are made of cylinder control bar and outer-hexagonal inner circular guide pipe, and boom member 35 is hexagon boom member.Heap
Core arranges 265 hexagon lattice cell positions, each fuel assembly 31, beryllium component 32, aluminium component 33, C&P systems 34 and water altogether
Lattice cell 35 respectively accounts for 1 position.11 box fuel assemblies 31 are loaded in the reactor core, centralized arrangement is using L12 as the heap of center position
The middle section of core is arranged in the position K10, K11, K12, K13, L11, L12, L13, M11, M12, M13, M14.The heap
16 box beryllium components 32 are loaded in core, around fuel assembly 31 arrange, be arranged in J9, J10, J11, J12, J13, K9, K14,
The position L10, L14, M10, M15, N11, N12, N13, N14, N15.72 box aluminium components 33 are loaded in the reactor core, surround beryllium component
32 arrangement, be arranged in 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、J16、K7、K15、K16、L6、L7、L8、L9、L15、L16、
L17、L18、M7、M8、M17、M18、N8、N9、N10、N16、N17、N18、P10、P12、P13、P14、P15、P17、P18、Q10、
The position Q11, Q12, Q14, Q16, Q17, Q18, R11, R12, R13, R14, R15, R16, R17, R18.12 are arranged in the reactor core
A C&P systems 34, around 32 arranged for interval of beryllium component between aluminium component 33, be arranged in H9, H11, I8, I13, K8,
The position K15, M9, M16, P11, P16, Q13, Q15.Fuel stack 31, beryllium component 32, aluminium component 33, control rod are removed in the reactor core
Outside lattice cell position shared by component 34, remaining position is arranged as boom member 35, and Whole core arranges 154 boom members 35 altogether.
As shown in Fig. 2, in hexagon thimble tube fuel reactor core aluminium component nuclear design certificate authenticity reactor core of the present invention
Arrange 12 C&P systems, including A stick group safety rod 36, B stick group shim rod 37, C stick group shim rod 38, D stick group shim rod
39 and E stick group regulating rod 310.A stick group safety rod 36 totally 4, is arranged in the position I8, I13, P11, P16；B stick group shim rod 37
Totally 2, it is arranged in the position H9, Q15；C stick group shim rod 38 totally 2, is arranged in the position H11, Q13；D stick group shim rod 39 totally 2
Root is arranged in the position K15, M9；E stick group regulating rod 310 totally 2, is arranged in the position K8, M16.
Hexagon beryllium component and aluminium component nuclear design certificate authenticity reactor core as shown in Figure 1 and hexagon beryllium as shown in Figure 2
Component 32 and 33 nuclear design certificate authenticity reactor core control rod of aluminium component arrangement, A stick group safety rod cold reactivity value are
1161pcm is greater than 1000pcm, meets the requirement that test reactor core criticality safety is worth safety rod.
Hexagon beryllium component 32 and 33 nuclear design certificate authenticity reactor core of aluminium component as shown in Figure 1, all mention in control rod
Out under reactor core state, reactor core effective multiplication factor nuclear design program calculated value is 1.0015, and 1 deviation of nominal value is less than 0.2%,
Think that reactor core is just critical.Carry out critical physical test according to the reactor core display, if C&P systems 34 all propose heap
Reactor core actual measurement effective multiplication factor is equal to nominal value 1 (and 1 deviation is less than 0.2%) under wick-like state, then illustrates nuclear design program pair
Beryllium component 32 and aluminium component 33 calculate accurately and reliably, do not need to be adjusted beryllium component 32 and 33 computation model of aluminium component；If
C&P systems 34 all propose under reactor core states that (and 1 deviation is greater than reactor core actual measurement effective multiplication factor not equal to nominal value 1
0.2%), then illustrate that nuclear design program is unsatisfactory for design requirement to beryllium component 32 and 34 computational accuracy of aluminium component, tune can be passed through
34 computation model of whole beryllium component 32 and aluminium component guarantees that nuclear design program calculated value is consistent with marginal test measured value.
When reactor core marginal test as shown in Figure 1 actual measurement effective multiplication factor be greater than 1 when (nuclear design program calculated value with face
Boundary's test result deviation is greater than 0.2%, and effective multiplication factor calculated value is less than normal), it can will be at aluminium component 33 and the J13 I12 at
32 transposition of beryllium component, reduce test reactor core effective multiplication factor calculated value to 0.9976, meet reactor core marginal test and want
It asks.If calculating deviation has exceeded above-mentioned adjusting range, using other measures so that reactor core is critical, for example, beryllium component 32 is dredged
Distribution sets or part C&P systems 34 is inserted into reactor core.
When reactor core marginal test as shown in Figure 1 actual measurement effective multiplication factor less than 1 when (nuclear design program calculated value with face
Boundary's test result deviation is greater than 0.2%, and effective multiplication factor calculated value is bigger than normal), it can be by the aluminium of the position H10, L8, L16, Q14
Component 33 replaces with boom member 35, improves test reactor core effective multiplication factor calculated value to 1.0057, meets reactor core marginal test
It is required that.If calculating deviation has exceeded above-mentioned adjusting range, other measures are used so that reactor core is critical, for example, increasing to heap in-core
Add more box beryllium components 32.
Above-described specific embodiment has carried out further the purpose of the present invention, technical scheme and beneficial effects
It is described in detail, it should be understood that being not intended to limit the present invention the foregoing is merely a specific embodiment of the invention
Protection scope, all within the spirits and principles of the present invention, any modification, equivalent substitution, improvement and etc. done should all include
Within protection scope of the present invention.
Claims (10)
1. hexagon beryllium component and aluminium component nuclear design certificate authenticity reactor core, which is characterized in that the reactor core includes fuel stack
Part (31), C&P systems (34), boom first (35), beryllium component (32) and aluminium component (33), the fuel assembly (31) are six
Side shape thimble tube fuel assembly, the C&P systems (34) are made of cylinder control bar and outer-hexagonal inner circular guide pipe,
The boom first (35) is hexagon boom member, and aluminium component (33) the hexagon aluminium component, the beryllium component (32) is six sides
Shape beryllium component, the reactor core arrange 265 positions, respectively 11 box fuel assemblies (31), 12 C&P systems (34), 16 altogether
Box beryllium component (32), 72 box aluminium components (33) and 154 boom members (34), 11 box fuel assembly (31) centralized arrangements are with L12
For the middle section of the reactor core of center position, 16 box beryllium components (32) are arranged around fuel assembly (31), 72 box aluminium components (33)
Arranged around 16 box beryllium components (32), 12 C&P systems (34) around beryllium component (32) arranged for interval aluminium component (33) it
Between, each fuel assembly (31), C&P systems (34), beryllium component (32), aluminium component (33) and boom first (35) respectively account for 1 position
It sets.
2. hexagon beryllium component according to claim 1 and aluminium component nuclear design certificate authenticity reactor core, which is characterized in that
The 11 box fuel assembly (31) is arranged in K10, K11, K12, K13, L11, L12, L13, M11, M12, M13, M14
It sets.
3. hexagon beryllium component according to claim 1 and aluminium component nuclear design certificate authenticity reactor core, which is characterized in that
The 16 box beryllium component (32) be arranged in J9, J10, J11, J12, J13, K9, K14, L10, L14, M10, M15, N11,
The position N12, N13, N14, N15.
4. hexagon beryllium component according to claim 1 and aluminium component nuclear design certificate authenticity reactor core, which is characterized in that
The 72 box aluminium component (33) be arranged in 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、J16、K7、K15、K16、L6、L7、L8、L9、
L15、L16、L17、L18、M7、M8、M17、M18、N8、N9、N10、N16、N17、N18、P10、P12、P13、P14、P15、P17、
The position P18, Q10, Q11, Q12, Q14, Q16, Q17, Q18, R11, R12, R13, R14, R15, R16, R17, R18.
5. hexagon beryllium component according to claim 1 and aluminium component nuclear design certificate authenticity reactor core, which is characterized in that
12 C&P systems (34) are by 4 A stick group safety rods (36), 2 B stick group shim rods (37), 2 C stick group shim rods
(38), 2 D stick group shim rods (39), 2 E stick group regulating rods (310) composition, 4 A stick group safety rods (36) be respectively arranged in
The position I8, I13, P11, P16,2 B stick group shim rods (37) are respectively arranged in the position H9, Q15,2 C stick group shim rods (38)
It is respectively arranged in the position H11, Q13,2 D stick group shim rods (39) are respectively arranged in the position K15, M9,2 E stick group regulating rods
(310) it is respectively arranged in the position K8, M16.
6. a kind of method of adjustment for examining reactor core as described in claim any one of 1-5, which is characterized in that obtaining reactor core respectively has
Imitate growth coefficient calculated value and measured value:
If C&P systems (34) all propose reactor core states under reactor core effective multiplication factor measured value and calculated value it is inclined
Difference is less than 0.2%, then nuclear design program calculates beryllium component (32) and aluminium component (33) accurate and reliable, does not need to beryllium component
(32) it is adjusted with aluminium component (33) computation model；
If C&P systems (34) all propose the measured value of reactor core effective multiplication factor and the deviation of calculated value under reactor core state
Greater than 0.2%, then nuclear design program is unsatisfactory for design requirement to beryllium component (32) and aluminium component (33) computational accuracy, needs to adjust
Beryllium component (32) and aluminium component (33) computation model, to guarantee nuclear design program calculated value and marginal test measured value one after adjustment
It causes.
7. examining the method for adjustment of reactor core according to claim 6, which is characterized in that when reactor core effective multiplication factor calculated value
Less than measured value, and when deviation is greater than 0.2%, by by beryllium component (32) the mutually transposition of aluminium component (33) and the place J13 at I12
It sets, reduces test reactor core effective multiplication factor.
8. examining the method for adjustment of reactor core according to claim 7, which is characterized in that when reactor core effective multiplication factor calculated value
Less than measured value, and when deviation is still greater than 0.2% after the adjustment of the method for adjustment described in the claim 7, by by beryllium component
(32) evacuation arranges or part C&P systems (34) is inserted into reactor core, reduces test reactor core effective multiplication factor.
9. examining the method for adjustment of reactor core according to claim 6, which is characterized in that when reactor core effective multiplication factor calculated value
Greater than measured value, and when deviation is greater than 0.2%, by the way that the aluminium component (33) of the position H10, L8, L16, Q14 is replaced with boom member
(34), test reactor core effective multiplication factor is improved.
10. examining the method for adjustment of reactor core according to claim 9, which is characterized in that when reactor core effective multiplication factor calculates
Value is greater than measured value, and when deviation is still greater than 0.2% after the adjustment of the method for adjustment described in the claim 9, by reactor core
Interior increase beryllium component (32) improves test reactor core effective multiplication factor.
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115394458A (en) * | 2022-08-26 | 2022-11-25 | 中国核动力研究设计院 | Ultra-high flux reactor core based on rod bundle type fuel assembly |
| CN115394459A (en) * | 2022-08-26 | 2022-11-25 | 中国核动力研究设计院 | Ultrahigh flux reactor core based on plate-shaped fuel assembly |
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| CN115394459A (en) * | 2022-08-26 | 2022-11-25 | 中国核动力研究设计院 | Ultrahigh flux reactor core based on plate-shaped fuel assembly |
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