CN113885071A - Method for verifying validity of reactor core subcritical supervision neutron detector - Google Patents
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- 238000000034 method Methods 0.000 title claims abstract description 27
- 238000001514 detection method Methods 0.000 claims abstract description 59
- 238000012360 testing method Methods 0.000 claims abstract description 35
- 230000004044 response Effects 0.000 claims abstract description 31
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 21
- 239000000446 fuel Substances 0.000 claims abstract description 11
- 230000002146 bilateral effect Effects 0.000 claims description 11
- 238000013459 approach Methods 0.000 claims description 5
- 239000000523 sample Substances 0.000 description 12
- 238000009434 installation Methods 0.000 description 10
- 230000000712 assembly Effects 0.000 description 5
- 238000000429 assembly Methods 0.000 description 5
- 238000012795 verification Methods 0.000 description 5
- 238000000926 separation method Methods 0.000 description 4
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 2
- 229910052796 boron Inorganic materials 0.000 description 2
- 230000013011 mating Effects 0.000 description 2
- 230000008569 process Effects 0.000 description 2
- 238000006748 scratching Methods 0.000 description 2
- 230000002393 scratching effect Effects 0.000 description 2
- 230000008878 coupling Effects 0.000 description 1
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- 238000005859 coupling reaction Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000006073 displacement reaction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 230000004907 flux Effects 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention discloses a method for verifying the validity of a reactor core subcritical supervision neutron detector, which comprises the following steps: s1, installing a detector of the nuclear instrument system and a detector of the temporary charging detection system at the periphery of the pressure vessel and in the pressure vessel respectively; s2, after the reactor water pool is filled with water, the primary neutron source assembly is placed in a pressure container; s3, sequentially moving the primary neutron source assembly to be close to the detector, and respectively performing active response tests on the detector of the nuclear instrument system and the temporary charging detection system; and S4, after the active response test is completed, placing the primary neutron source assembly at a preset position far away from all the detectors in the pressure vessel. The method avoids using a strong neutron source to test the nuclear power plant primary fuel loading reactor core subcritical supervision neutron detector, avoids extra irradiation dose caused by operating the neutron source by personnel, and avoids the risk caused by installing the temporary loading detection system under the condition that a reactor water pool is full of water.
Description
Technical Field
The invention relates to the technical field of nuclear power system debugging, in particular to an effectiveness verification method for a reactor core subcritical supervision neutron detector.
Background
In the current mainstream pressurized water reactor nuclear power plant, a temporary loading detection system is used during the first loading period, and the temporary loading detection system and a nuclear instrument system (source range channel) are used together to monitor the neutron flux in the reactor during the loading period so as to ensure that the reactor core is in a subcritical state in the whole loading process and prevent the reactor core from accidentally reaching the critical state during the loading period. The availability of the temporary charge detection system and the nuclear instrumentation system are prerequisites for charging. In order to ensure that the temporary charging detection system is available, an active response test (neutron source) needs to be carried out on the temporary charging detection system within 8 hours before charging so as to ensure that the system works normally; in order to ensure the availability of the nuclear instrument system, besides the system body experiment, a neutron source response test is also required to be carried out on the nuclear instrument system so as to ensure the normal work of the system.
Temporary charging detection system: in order to meet the requirements of relevant procedures, after the charging time is determined (the reactor pool is filled with boron water), a neutron radioactive source response test is carried out on the temporary charging detection system on a 20-meter platform in the nuclear island plant, after the test is qualified, the detector is installed to a specified position through manpower under the state that the reactor pool is full of water, and then cable connection and fixation are carried out, and the system is put into operation.
Nuclear instrumentation system: under the condition that the verification of the cabinet body is completed, a neutron source is used for a response test on a 20-meter platform of the nuclear island to ensure that the system is usable.
The neutron source response test for the temporary charging detection system and the nuclear instrument system has the following defects:
(1) performing neutron source response test in a nuclear island plant can cause extra irradiation measurement and corresponding risks;
(2) during the neutron source response test, the nuclear island plant needs to be closed, other work cannot be carried out, and a main line is occupied;
(3) the detector, the cable and the related components in the detection system are arranged temporarily, the mass is large, the detector, the cable and the related components are arranged under the condition that the reactor pool is full of water, risks such as collision of the detector and the related components with the components in the reactor, falling of an operator, introduction of foreign matters and the like exist, and the installation precision of the detector cannot be guaranteed.
(4) And the neutron source response test of the nuclear instrument system needs to be carried out by using additional equipment.
Disclosure of Invention
The invention aims to solve the technical problem of providing a method for verifying the validity of a reactor core subcritical supervision neutron detector, which avoids the installation risk of the detector and the generation of additional irradiation metering risk.
The technical scheme adopted by the invention for solving the technical problems is as follows: the method for verifying the validity of the reactor core subcritical supervision neutron detector comprises the following steps:
s1, installing a detector of the nuclear instrument system and a detector of the temporary charging detection system at the periphery of the pressure vessel and in the pressure vessel respectively;
s2, after the reactor water pool is filled with water, placing the primary neutron source assembly into the pressure container;
s3, sequentially moving the primary neutron source assembly to enable the primary neutron source assembly to be close to the detector of the nuclear instrument system and the detector of the temporary charging detection system, and respectively carrying out active response tests on the detector of the nuclear instrument system and the detector of the temporary charging detection system;
and S4, after the active response test is completed, placing the primary neutron source assembly at a preset position far away from all detectors in the pressure vessel.
Preferably, in step S1, before installing the detector of the temporary charge detection system, a reactor lower member is installed into the pressure vessel;
in step S2, the bottom of the primary neutron source assembly is fitted to the bottom plate of the reactor lower member.
Preferably, step S1 includes:
s1.1, installing a detector of a nuclear instrument system at the periphery of a pressure container;
s1.2, installing a reactor lower component into the pressure vessel;
s1.3, installing a detector of a temporary charge detection system on the inner wall of the pressure vessel and above the bottom plate of the reactor lower component.
Preferably, in step S1.3, the height of the detector of the temporary charge detection system above the floor of the reactor lower member has the same value as the quarter length of the fuel assemblies to be loaded by the pressure vessel.
Preferably, in step S3, moving the primary neutron source assembly through the PMC cart; the primary neutron source assembly is cooperatively positioned on the floor of the reactor lower member after each movement.
Preferably, in step S3, after each movement of the primary neutron source assembly close to the detector of the nuclear instrumentation system or the detector of the temporary charge detection system, the bottom of the primary neutron source assembly is fitted in a corresponding position on the bottom plate of the reactor lower member, and the primary neutron source assembly and the corresponding position satisfy a bilateral fitting and/or a non-spike fitting.
Preferably, in step S4, after the active response test is completed, the bottom of the primary neutron source assembly is fitted to the bottom plate of the reactor lower component at a predetermined position, and the primary neutron source assembly and the reactor lower component satisfy bilateral fitting and/or non-spike fitting.
Preferably, step S3 includes:
s3.1, moving the primary neutron source component to enable the primary neutron source component to be close to a detector of the nuclear instrument system, and carrying out an active response test on the nuclear instrument system;
and S3.2, moving the primary neutron source assembly to be close to a detector of the temporary charge detection system, and carrying out an active response test on the temporary charge detection system.
Preferably, in step S1, the probes of the nuclear instrumentation system include at least two probes spaced apart along the circumference of the pressure vessel;
the detectors of the temporary charge detection system comprise at least three detectors which are distributed at intervals along the circumferential direction of the pressure vessel;
in the step S3.1, sequentially moving the primary neutron source assembly to enable the primary neutron source assembly to gradually approach all detectors of the nuclear instrument system;
and S3.2, sequentially moving the primary neutron source assembly to enable the primary neutron source assembly to gradually approach all detectors of the temporary charging detection system.
Preferably, in step S2, after the reactor pool is filled with water, it is confirmed that the detector of the temporary charge detection system is not displaced and then placed in the primary neutron source assembly.
The method for verifying the effectiveness of the reactor core subcritical supervision neutron detector is used for testing the reactor core subcritical supervision neutron detector loaded by the first fuel of a nuclear power plant, the detectors of a nuclear instrument system and a temporary loading detection system are installed on designated positions before water is injected into a reactor pool, and a primary neutron source assembly is used for performing active response test on the two systems to realize effective verification of the detectors; the method avoids the use of a strong neutron source for testing the nuclear power plant primary fuel loading reactor core subcritical supervision neutron detector and avoids the risk caused by the installation of a temporary loading detection system under the condition that a reactor water pool is full of water; on the premise of not increasing additional equipment and investment, the first charging critical path can be saved for about 24 hours, meanwhile, the extra irradiation dose caused by operating a neutron source by personnel is avoided, and the risk that the lower component in the reactor is damaged can be avoided.
Drawings
The invention will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a flow chart of the method for verifying the validity of a reactor core subcritical supervision neutron detector according to the invention;
FIG. 2 is a schematic diagram of the installation of the detector on the pressure vessel in the validity verification method of the reactor core subcritical supervision neutron detector of the invention;
FIG. 3 is a schematic view of the installed position of the detector relative to the lower reactor component in accordance with an embodiment of the present invention.
Detailed Description
For a more clear understanding of the technical features, objects and effects of the present invention, embodiments of the present invention will now be described in detail with reference to the accompanying drawings.
Referring to fig. 1 and 2, the method for verifying the validity of the subcritical supervision neutron detector of the reactor core of the invention is carried out before the fuel assemblies are loaded for the first time, and the method can comprise the following steps:
s1, installing the detector (source range detector) 10 of the nuclear instrumentation system and the detector 20 of the temporary charge detection system at the periphery of the pressure vessel 100 and in the pressure vessel 100, respectively.
Wherein a lower reactor component (not shown) is installed into the pressure vessel 100 prior to installation of the probe 20 of the temporary charge detection system. The whole lower component of the reactor can be in a hollow cylinder structure, and the bottom plate of the lower component of the reactor can be a support plate with grid-shaped positioning grooves and used for matching and positioning subsequent primary neutron source assemblies and matching and positioning subsequent loaded fuel assemblies.
Specifically, the step S1 may include:
s1.1, installing the probe 10 of the nuclear instrumentation system on the periphery of the pressure vessel 100, such as in a concrete sidewall located on the periphery of the pressure vessel 100.
Generally, the probe 10 of the nuclear instrumentation system comprises at least two. When installed, all of the probes 10 of the nuclear instrumentation system are spaced circumferentially along the pressure vessel 100 and positioned about the periphery of the pressure vessel 100. The angle of separation (angle) between the probes 10 varies depending on the number of probes 10. For example, when there are two detectors 10, the two detectors 10 are spaced at an angle (included angle) of 180 °; when there are three detectors 10, the angular separation may be 90 °.
It is understood that the number and specific installation positions of the probes 10 of the nuclear instrumentation system are set according to the core type.
In addition, after the installation of the detector 10 of the nuclear instrument system is completed, the nuclear instrument system is also subjected to routine tests to ensure that the nuclear instrument system can work normally.
S1.2, installing the reactor lower component into the lower end of the pressure vessel 100. Wherein the outer periphery of the reactor lower member may be fixed to the inner peripheral wall surface of the pressure vessel 100 by a coupling assembly or the like.
S1.3, mounting the detector 20 of the temporary charge detection system on the inner wall of the pressure vessel 100 and above the floor of the lower reactor component.
The detector 20 of the temporary charge detection system includes at least three. When installed, all of the probes 20 of the temporary charge detection system are spaced circumferentially along the pressure vessel 100 and positioned on the inner wall of the pressure vessel 100. The angle of separation (angle) between the detectors 20 varies depending on the number of detectors 20. For example, when there are three detectors 20, the separation angle may be 90 °. It will be appreciated that the number and specific installation locations of the probes 20 of the temporary charge detection system are set according to the type of core.
Preferably, the height of the detector 20 of the temporary charge detection system above the floor of the lower reactor component within the pressure vessel 100 has the same value as the quarter length of the fuel assemblies to be loaded by the pressure vessel 100.
The cabinet 21 of the temporary charge detection system is placed on a 20-meter platform 300 of the nuclear island building, and the cabinet 21 is connected with the detector 20 of the temporary charge detection system through a cable 22. After the probe 20 is installed in the pressure vessel 100, the cable 22 is also positioned to avoid displacement, shaking, etc.
S2, filling the reactor pool 200 with water (boron water), and placing the primary neutron source assembly into the pressure vessel 100.
The primary neutron source assembly is also selected based on the core type and may be temporarily placed in the reactor pool 200 prior to placement in the pressure vessel 100.
The step S2 further includes: after the reactor pool 200 is filled with water, the primary neutron source assembly is replaced after confirming that the detector 20 of the temporary charge detection system has not been displaced.
When the primary neutron source assembly is placed, the bottom of the primary neutron source assembly is fitted to the bottom plate of the reactor lower member.
S3, sequentially moving the primary neutron source assembly to enable the primary neutron source assembly to be close to the detector 10 of the nuclear instrument system and the detector 20 of the temporary charging detection system, and respectively performing active response tests on the nuclear instrument system and the temporary charging detection system to ensure that a source range channel of the nuclear instrument system and a channel of the temporary charging detection system work normally.
In step S3, the primary neutron source module is moved by a PMC (Fuel handling and Storage) cart. The primary neutron source assembly is cooperatively positioned on the floor of the reactor lower member after each movement. During moving, the primary neutron source assembly is moved upwards to be separated from the bottom plate of the lower reactor component, then the primary neutron source assembly is horizontally moved to the accessories of the detectors 10 and 20, and then the primary neutron source assembly is lowered to be matched and positioned on the bottom plate of the lower reactor component.
Step S3 may further include:
and S3.1, moving the primary neutron source assembly to be close to a detector 10 of the nuclear instrument system, and carrying out an active response test on the nuclear instrument system.
The detectors 10 combined with the nuclear instrumentation system are usually two or more, and when the primary neutron source assembly is moved, the primary neutron source assembly is moved in sequence, so that the primary neutron source assembly is gradually close to all the detectors 10 of the nuclear instrumentation system, and the active response test of all the source range channels of the nuclear instrumentation system is completed.
After each movement of the primary neutron source assembly close to the detector 10 of the nuclear instrumentation system, the bottom of the primary neutron source assembly is fitted to a corresponding position on the bottom plate of the reactor lower component, and the primary neutron source assembly (bottom) and the corresponding position satisfy bilateral fitting and/or non-spike fitting. Preferably, the primary neutron source assembly and the corresponding position should meet the requirements of bilateral matching and non-spike matching as much as possible.
The bilateral fit means that two surfaces of the primary neutron source component are in contact with the lower component of the reactor to increase the stability of the primary neutron source component; the non-sharp edge matching is that the edge of the primary neutron source component can not be directly opposite to the protruding edge of the reactor lower component, so as to prevent damage caused by mutual scratching.
And S3.2, moving the primary neutron source assembly to be close to the detector 20 of the temporary charge detection system, and carrying out an active response test on the temporary charge detection system.
In combination, the number of detectors 20 of the temporary charge detection system is usually three or more, and when the primary neutron source assembly is moved, the primary neutron source assembly is moved in sequence, so that the primary neutron source assembly is gradually close to all the detectors 20 of the temporary charge detection system, and the active response test of all the channels of the temporary charge detection system is completed.
After each movement of the primary neutron source assembly close to the detector 20 of the temporary charge detection system, the bottom of the primary neutron source assembly fits in a corresponding position on the bottom plate of the reactor lower component, and the primary neutron source assembly (bottom) fits bilaterally and/or is not sharp with the corresponding position. Preferably, the primary neutron source assembly and the corresponding position should meet the requirements of bilateral matching and non-spike matching as much as possible.
The bilateral fit means that two surfaces of the primary neutron source component are in contact with the lower component of the reactor to increase the stability of the primary neutron source component; the non-sharp edge matching is that the edge of the primary neutron source component can not be directly opposite to the protruding edge of the reactor lower component, so as to prevent damage caused by mutual scratching.
The steps S3.1 and S3.2 may be performed in sequence, or may be performed in reverse sequence, that is, the order of the active response tests of the two systems is not limited.
The active response test operation mode, the judgment standard and the like of the nuclear instrument system and the temporary charging detection system can be realized by adopting the prior art.
S4, after the active response test is completed, the primary neutron source assembly is moved and placed in the pressure vessel 100 at a predetermined location remote from all of the detectors 10, 20.
In a predetermined position, the bottom of the primary neutron source assembly is mated to the reactor lower member, and the primary neutron source assembly (bottom) and the reactor lower member (floor) meet a bilateral mating and/or a non-spike mating. Preferably, the primary neutron source assembly and the reactor lower member are positioned as close as possible to a bilateral fit and a non-frontal fit.
After the reactor core subcritical supervision neutron detector validity verification method is completed, subsequent fuel assembly loading can be carried out, namely: the fuel assembly is mounted into the pressure vessel 100 and positioned on the reactor lower component.
The invention is further illustrated by the following specific examples.
As shown in fig. 3, which shows a top view of the reactor lower member, each square is a positioning slot on the bottom plate of the reactor lower member. Wherein, A, B position is the detector installation position of nuclear instrument system respectively, C, D, E position is the installation position of the detector of temporary charging detecting system respectively, and serial numbers 1-6 are the positioning position of primary neutron source subassembly respectively.
When the active response test is carried out, the primary neutron source assembly can be moved according to the sequence of 1-2-3-4-5 so as to be close to each detector in sequence, and the active response test is carried out on the nuclear instrument system and the temporary charge detection system. Finally, the primary neutron source assembly is placed at location 6, where location 6 is remote from locations 1-5, as well as from all detectors.
The above description is only an embodiment of the present invention, and not intended to limit the scope of the present invention, and all modifications of equivalent structures and equivalent processes performed by the present specification and drawings, or directly or indirectly applied to other related technical fields, are included in the scope of the present invention.
Claims (10)
1. The method for verifying the validity of the reactor core subcritical supervision neutron detector is characterized by comprising the following steps:
s1, installing a detector of the nuclear instrument system and a detector of the temporary charging detection system at the periphery of the pressure vessel and in the pressure vessel respectively;
s2, after the reactor water pool is filled with water, placing the primary neutron source assembly into the pressure container;
s3, sequentially moving the primary neutron source assembly to enable the primary neutron source assembly to be close to the detector of the nuclear instrument system and the detector of the temporary charging detection system, and respectively carrying out active response tests on the detector of the nuclear instrument system and the detector of the temporary charging detection system;
and S4, after the active response test is completed, placing the primary neutron source assembly at a preset position far away from all detectors in the pressure vessel.
2. The method for verifying the validity of the in-core subcritical supervised neutron detector according to claim 1, wherein in step S1, before installing the detector of the temporary charge detection system, a reactor lower component is installed into the pressure vessel;
in step S2, the bottom of the primary neutron source assembly is fitted to the bottom plate of the reactor lower member.
3. The method for verifying the validity of the in-core subcritical supervised neutron detector according to claim 2, wherein the step S1 comprises:
s1.1, installing a detector of a nuclear instrument system at the periphery of a pressure container;
s1.2, installing a reactor lower component into the pressure vessel;
s1.3, installing a detector of a temporary charge detection system on the inner wall of the pressure vessel and above the bottom plate of the reactor lower component.
4. The method for verifying the validity of the in-core subcritical supervised neutron detector according to claim 3, characterized in that in step S1.3, the value of the height of the detector of the temporary charge detection system on the bottom plate of the reactor lower member is the same as the value of the quarter length of the fuel assembly to be loaded by the pressure vessel.
5. The method for verifying the validity of the subcritical supervised neutron detector in the reactor core according to claim 2, wherein in step S3, the primary neutron source assembly is moved by a PMC trolley; the primary neutron source assembly is cooperatively positioned on the floor of the reactor lower member after each movement.
6. The method for verifying the validity of the in-core subcritical supervised neutron detector according to claim 2, wherein in step S3, after each movement of the primary neutron source assembly to approach the detector of the nuclear instrumentation system or the detector of the temporary charge detection system, the bottom of the primary neutron source assembly is fitted on the corresponding position of the bottom plate of the reactor lower component, and the primary neutron source assembly and the corresponding position satisfy bilateral fitting and/or non-front fitting.
7. The method for verifying the validity of the in-core subcritical supervised neutron detector according to claim 2, wherein in step S4, after completing the active response test, the bottom of the primary neutron source assembly is fitted on the bottom plate of the reactor lower component at a predetermined position, and the primary neutron source assembly and the reactor lower component satisfy bilateral fitting and/or non-spike fitting.
8. The method for verifying the validity of the in-core subcritical supervised neutron detector according to any one of claims 1 to 7, wherein the step S3 comprises:
s3.1, moving the primary neutron source component to enable the primary neutron source component to be close to a detector of the nuclear instrument system, and carrying out an active response test on the nuclear instrument system;
and S3.2, moving the primary neutron source assembly to be close to a detector of the temporary charge detection system, and carrying out an active response test on the temporary charge detection system.
9. The method for verifying the validity of the in-core subcritical supervised neutron detector according to claim 8, wherein in the step S1, the detectors of the nuclear instrumentation system comprise at least two detectors which are distributed at intervals along the circumference of the pressure vessel;
the detectors of the temporary charge detection system comprise at least three detectors which are distributed at intervals along the circumferential direction of the pressure vessel;
in the step S3.1, sequentially moving the primary neutron source assembly to enable the primary neutron source assembly to gradually approach all detectors of the nuclear instrument system;
and S3.2, sequentially moving the primary neutron source assembly to enable the primary neutron source assembly to gradually approach all detectors of the temporary charging detection system.
10. The method for verifying the validity of the in-core subcritical supervised neutron detector according to any one of claims 1 to 7, wherein in step S2, after the reactor water pool is filled with water, it is confirmed that the detector of the temporary charge detection system is not displaced and then placed in the primary neutron source assembly.
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115424745A (en) * | 2022-09-09 | 2022-12-02 | 中国核动力研究设计院 | Nuclear instrument system suitable for neutron fluence rate measurement of high-flux reactor |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2011107105A (en) * | 2009-11-20 | 2011-06-02 | Toshiba Corp | Nuclear instrumentation system |
| CN111312419A (en) * | 2020-03-27 | 2020-06-19 | 江苏核电有限公司 | Core loading method for pressurized water reactor primary reactor core without additional primary neutron source |
| CN112130194A (en) * | 2020-08-20 | 2020-12-25 | 中国原子能科学研究院 | Quick verifying attachment of neutron detector |
-
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- 2021-09-02 CN CN202111028749.3A patent/CN113885071A/en active Pending
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2011107105A (en) * | 2009-11-20 | 2011-06-02 | Toshiba Corp | Nuclear instrumentation system |
| CN111312419A (en) * | 2020-03-27 | 2020-06-19 | 江苏核电有限公司 | Core loading method for pressurized water reactor primary reactor core without additional primary neutron source |
| CN112130194A (en) * | 2020-08-20 | 2020-12-25 | 中国原子能科学研究院 | Quick verifying attachment of neutron detector |
Non-Patent Citations (1)
| Title |
|---|
| 杨晓鹏;刘明忠;: "福清1号机组首次堆芯装料中子探测效率经验反馈", 科技视界, no. 07, 5 March 2016 (2016-03-05) * |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115424745A (en) * | 2022-09-09 | 2022-12-02 | 中国核动力研究设计院 | Nuclear instrument system suitable for neutron fluence rate measurement of high-flux reactor |
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