CN116469589B - Subcritical state rod carving method based on critical rod reaching process - Google Patents
Subcritical state rod carving method based on critical rod reaching process Download PDFInfo
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- 238000000034 method Methods 0.000 title claims abstract description 69
- 230000008569 process Effects 0.000 title claims abstract description 45
- 238000005259 measurement Methods 0.000 claims abstract description 49
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 claims abstract description 20
- 229910052796 boron Inorganic materials 0.000 claims abstract description 20
- 230000008859 change Effects 0.000 claims abstract description 5
- 230000009257 reactivity Effects 0.000 claims description 18
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 10
- 238000004088 simulation Methods 0.000 claims description 9
- 238000004364 calculation method Methods 0.000 claims description 7
- 238000003113 dilution method Methods 0.000 claims description 7
- 230000035755 proliferation Effects 0.000 claims description 4
- 230000008901 benefit Effects 0.000 abstract description 5
- 238000010586 diagram Methods 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 238000005530 etching Methods 0.000 description 1
- 230000008439 repair process Effects 0.000 description 1
- 230000009466 transformation Effects 0.000 description 1
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
A subcritical state rod carving method based on a critical rod reaching process realizes the scale of the value of a control rod through the counting monitored by a source range detector in real time in the critical rod reaching process. According to the boron concentration and the control rod position information of the reactor core in the subcritical rod lifting process, calculating values of a source range detector counting multiplication factor in a target subcritical state are obtained by adopting reactor core calculation software, the calculated values are applied to source range detector counting actual measurement values in corresponding states, subcritical degree actual measurement values in subcritical states are obtained, and control rod position change among different subcritical states is combined to complete control rod value measurement. The method can finish the value measurement of the control rod in the subcritical state, can save the step of the value measurement of the control rod after the critical state, greatly saves the time for starting the physical test, and has higher economic benefit.
Description
Technical Field
The invention relates to the technical field of pressurized water reactor core physical calculation, in particular to a subcritical state rod carving method based on a critical rod reaching process.
Background
After the commercial nuclear power station is subjected to major repair and material replacement, a starting physical test is required to be performed under the condition of zero power, key physical parameters of the reactor are verified, and then the power can be gradually increased until the full power operation is performed. Thus, the long start-up physical test time can greatly impact the economic benefits of the reactor. The control rod value measurement (immediate rod test) is an important content of a commercial pressurized water reactor starting physical test, and is used for verifying the coincidence degree of an actual measurement value and a design value of the control rod value, and the measurement of the control rod value directly relates to the operation safety of a reactor. At present, the existing methods are all to measure the value of the control rod by singly taking out the control rod for a period of time in a critical state after the reactor reaches the critical state, and the adopted methods comprise a boron dilution method, a rod replacement method and a dynamic rod etching method, but all have the problem of occupying the starting physical test time, so that the economic benefit of the nuclear power station is greatly influenced.
Disclosure of Invention
Aiming at the practical problem that the prior methods are used for measuring the value of the control rod independently after reaching the critical state, which results in longer starting physical test time, the invention aims to provide a subcritical state rod carving method based on the critical rod lifting process, and the method realizes the value measurement of the control rod through the counting data of a source range detector in the subcritical rod lifting process, so that the time for measuring the value of the control rod after reaching the critical state can be saved.
In order to achieve the above purpose, the invention adopts the following technical scheme:
a subcritical state rod carving method based on a critical rod lifting process can realize the calibration of control rod value according to the actual measurement value counted by a source range detector in the critical rod lifting process of a pressurized water reactor; the method comprises the following steps:
step 1: and according to the boron concentration and the control rod position information in the critical rod lifting process, performing subcritical simulation calculation by adopting core calculation software to obtain a calculated value and a reactivity calculated value of a source range detector counting multiplication factor in a target subcritical state. This step is mainly subdivided into the following parts:
1) Continuously extracting control rods in a critical process of a pressurized water reactor nuclear power plant, and recording rod position information and boron concentration information of the control rods in the critical process, wherein a subcritical state for measuring the value of the control rods is called a target subcritical state, and the total number of the target subcritical states is recorded as N;
2) After the control rod is continuously put out, the boron dilution process of the nuclear power plant is further critical, after the control rod is continuously put out, the state before the boron dilution process is a reference state, the reference state is marked as Ref, and the control rod position information and the boron concentration information of the reference state are recorded;
3) Based on the control rod position and the boron concentration of the target subcritical state and the reference state, performing neutron simulation calculation by adopting core calculation software, and respectively solving a fixed neutron source equation and a characteristic value equation;
4) Neutron simulation results based on reactor core calculation software are used for obtaining a calculated value M of the n-th target subcritical state source range detector count n c Calculated value of source range detector count for reference stateAnd the calculated value of the reactivity of the nth target subcritical state +.>
5) Calculating the calculated value Q of the source range detector count multiplication factor of the nth target subcritical state according to the formula (1) n c 。
Step 2: and obtaining the actual measurement value of the proliferation factor counted by the source range detector in the target subcritical state according to the actual measurement value counted by the source range detector in the critical rod lifting process. This step is mainly subdivided into the following parts:
1) The method comprises the steps that a source range detector is adopted to monitor the reactor core state in the process of reaching a critical rod lifting of a pressurized water reactor nuclear power plant, and the actual measurement value counted by the source range detector in the process of reaching the critical rod lifting is recorded;
2) The counting actual measurement value of the source range detector is directly measured, so that signal fluctuation is large due to noise influence, the counting actual measurement value of the source range detector is processed by adopting a denoising method, the change of the counting actual measurement value of the relatively smooth source range detector along with time is obtained, and the subcritical rod carving precision is ensured;
3) Selecting an actual measurement value M of the source range detector count of the target subcritical state from the actual measurement value of the source range detector count after the denoising process n m And the measured value of the source range detector count for the reference state
4) Obtaining the actual measurement value Q of the source range detector count multiplication factor of the nth target subcritical state according to the formula (2) n m ；
Step 3: counting multiplication factors according to the source range detector of the nth target subcritical state obtained in the step 1Calculated value Q of (2) n c Calculated reactivity of nth target subcritical stateAnd the measured value Q of the source range detector count multiplication factor of the nth target subcritical state obtained in the step 2 n m Obtaining the actually measured value of the reactivity of the nth target subcritical state by the formula (3)>
Step 4: according to the control rod position information of different target subcritical states and the reactivity actual measurement value of the nth target subcritical state obtained in the formula (3) in the step (3)Calculating the value W of the control rod n As shown in equation (4).
Compared with the prior art, the invention has the following advantages:
1. the reactor core critical-reaching rod-extracting process adopted by the invention is a normal critical-reaching operation flow after the material change of the nuclear power plant, any other operation flow is not required to be added on the original regulation, the counting data of the source range detector in the process also exist per se, and the nuclear power plant is required to monitor the reactor core state according to the data of the source range detector, so that the method of the invention is not required to be independently used for carrying out any additional transformation and operation on the source range detector.
2. The invention completes the control rod value measurement in the process of reaching the critical rod lifting of the reactor core, avoids the control rod value measurement by singly taking out time after the critical, saves a great amount of time for starting the physical test, accelerates the process of lifting the reactor core to full power, and has higher economic benefit.
3. The control rod value of the invention is finished under subcritical conditions, thereby greatly guaranteeing the safety of the reactor core and avoiding the safety risk brought by the movement of the control rod under critical conditions.
Drawings
FIG. 1 is a sub-critical state rod carving process flow based on a reach critical rod lifting process.
Fig. 2 is a schematic diagram of a radial arrangement of source span detectors.
Fig. 3 is a schematic diagram of the axial arrangement of the source span detector.
Detailed Description
The invention is described in further detail below with reference to the attached drawings and detailed description:
the invention realizes control rod value measurement by counting data of a source range detector in a subcritical rod lifting process, and the specific steps are shown in fig. 1, and comprise the following steps:
step 1: and according to the boron concentration and the control rod position information in the critical rod lifting process, performing subcritical simulation calculation by adopting core calculation software to obtain a calculated value and a reactivity calculated value of a source range detector counting multiplication factor in a target subcritical state. This step is mainly subdivided into the following parts:
1) In the critical process of the pressurized water reactor nuclear power plant, control rods are continuously put forward, the rod position information and the boron concentration information of the control rods in the process are recorded, wherein the subcritical state for measuring the value of the control rods is called a target subcritical state, and the total number of the target subcritical states is recorded as N. In this embodiment, the core includes nine groups of control rods, named G1, G2, N1, N2, R, SA, SB, SC, SD, respectively, and the initial state of continuously extracting the control rods in the critical process is that all the control rods are located at the bottom of the core, the end state is that the R rod is located at 150 steps, and the remaining rod groups are located at the top of the core.
2) After the control rod is continuously put out, the boron dilution process of the nuclear power plant is further critical, after the control rod is continuously put out, the state before the boron dilution process is the reference state, the reference state is marked as Ref, and the control rod position information and the boron concentration information of the reference state are recorded. In this embodiment, the reference state is that the R rods are located at 150 steps and the remaining rod sets are located at the top of the core.
3) Based on the control rod position and the boron concentration of the target subcritical state and the reference state, neutron simulation calculation is performed by adopting core calculation software, and a fixed neutron source equation and a characteristic value equation are respectively solved.
4) Neutron simulation results based on reactor core calculation software are used for obtaining a calculated value M of the n-th target subcritical state source range detector count n c Calculated value of source range detector count for reference stateAnd the calculated value of the reactivity of the nth target subcritical state +.>Where n represents the nth subcritical state.
5) Calculating the calculated value Q of the source range detector count multiplication factor of the nth target subcritical state according to the formula (1) n c 。
Step 2: and obtaining the actual measurement value of the proliferation factor counted by the source range detector in the target subcritical state according to the actual measurement value counted by the source range detector in the critical rod lifting process. This step is mainly subdivided into the following parts:
1) The pressurized water reactor nuclear power plant adopts a source range detector to monitor the reactor core state in the process of reaching the critical rod lifting, and records the actual measurement value counted by the source range detector in the process of reaching the critical rod lifting. In this embodiment, two source span detectors are arranged around the reactor, radially as shown in fig. 2, and axially as shown in fig. 3.
2) The counting actual measurement value of the source range detector is directly measured, so that signal fluctuation is large due to noise influence, the counting actual measurement value of the source range detector is processed by adopting a denoising method, the change of the counting actual measurement value of the relatively smooth source range detector along with time is obtained, and the subcritical rod carving precision is ensured;
3) Selecting an actual measurement value M of the source range detector count of the target subcritical state from the actual measurement value of the source range detector count after the denoising process n m And the measured value of the source range detector count for the reference state
4) Obtaining the actual measurement value Q of the count multiplication factor of the off-stack detector in the nth target subcritical state according to the formula (2) n m 。
Step 3: calculating the value Q of the multiplication factor counted by the source range detector according to the nth target subcritical state obtained in the step 1 n c Calculated reactivity of nth target subcritical stateAnd the measured value Q of the source range detector count multiplication factor of the nth target subcritical state obtained in the step 2 n m Obtaining the actually measured value of the reactivity of the nth target subcritical state by the formula (3)>
Step 4: according to the control rod position information of different target subcritical states and the reactivity actual measurement value of the nth target subcritical state obtained in the formula (3) in the step (3)Calculating the value W of the control rod n As shown in equation (4).
In this example, SA, SB, SC, SD and the total value of the power adjustment bar sets (G1, G2, N1, N2) are measured as shown in the following table.
From the results, the method can obtain a control rod value measurement result with higher precision in a subcritical state, and has feasibility of industrial application.
Claims (2)
1. A subcritical state rod carving method based on a critical rod reaching process is characterized by comprising the following steps of: the graduation of the control rod value can be realized according to the actual measurement value counted by the source range detector in the process of reaching the critical rod lifting of the pressurized water reactor; the method comprises the following steps:
step 1: according to the boron concentration and the control rod position information in the critical rod lifting process, performing subcritical simulation calculation by adopting core calculation software to obtain a calculated value and a reactivity calculated value of a source range detector counting multiplication factor in a target subcritical state;
step 2: obtaining an actual measurement value of a counting multiplication factor of a source range detector in a target subcritical state according to the actual measurement value of the counting of the source range detector in the critical rod lifting process;
step 3: obtaining a target subcritical state reactivity actual measurement value according to the calculated value and the reactivity calculated value of the proliferation factor counted by the source range detector in the target subcritical state in the step 1 and the actual measurement value of the proliferation factor counted by the source range detector in the target subcritical state in the step 2;
step 4: combining the control rod position information of different target subcritical states and the actual measurement value of the target subcritical state reactivity in the step 3 to realize control rod value measurement;
the implementation process of the step 1 is as follows:
1) Continuously extracting control rods in a critical process of a pressurized water reactor nuclear power plant, and recording rod position information and boron concentration information of the control rods in the critical process, wherein a subcritical state for measuring the value of the control rods is called a target subcritical state, and the total number of the target subcritical states is recorded as N;
2) After the control rod is continuously put out, the boron dilution process of the nuclear power plant is further critical, after the control rod is continuously put out, the state before the boron dilution process is a reference state, the reference state is marked as Ref, and the control rod position information and the boron concentration information of the reference state are recorded;
3) Based on the control rod position and the boron concentration of the target subcritical state and the reference state, performing neutron simulation calculation by adopting core calculation software, and respectively solving a fixed neutron source equation and a characteristic value equation;
4) Neutron simulation results based on reactor core calculation software are used for obtaining a calculated value M of the n-th target subcritical state source range detector count n c Calculated value of source range detector count for reference stateAnd the calculated value of the reactivity of the nth target subcritical state +.>
5) Calculating the calculated value Q of the source range detector count multiplication factor of the nth target subcritical state according to the formula (1) n c ；
The implementation process of the step 2 is as follows:
1) The method comprises the steps that a source range detector is adopted to monitor the reactor core state in the process of reaching a critical rod lifting of a pressurized water reactor nuclear power plant, and the actual measurement value counted by the source range detector in the process of reaching the critical rod lifting is recorded;
2) The counting actual measurement value of the source range detector is directly measured, so that signal fluctuation is large due to noise influence, the counting actual measurement value of the source range detector is processed by adopting a denoising method, the change of the counting actual measurement value of the relatively smooth source range detector along with time is obtained, and the subcritical rod carving precision is ensured;
3) Selecting an actual measurement value M of the source range detector count of the target subcritical state from the actual measurement value of the source range detector count after the denoising process n m And the measured value of the source range detector count for the reference state
4) Obtaining the actual measurement value Q of the source range detector count multiplication factor of the nth target subcritical state according to the formula (2) n m ；
The implementation process of the step 3 is as follows:
calculating the value Q of the multiplication factor counted by the source range detector according to the obtained nth target subcritical state n c Calculated reactivity of nth target subcritical stateAnd the measured value Q of the multiplication factor counted by the source range detector in the nth target subcritical state n m Obtaining the actually measured value of the reactivity of the nth target subcritical state by the formula (3)>
2. The method according to claim 1, characterized in that: the implementation process of the step 4 is as follows:
according to the control rod position information of different target subcritical states and the obtained reactivity actual measurement value of the nth target subcritical stateCalculating the value W of the control rod n As shown in formula (4):
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Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP1422723A1 (en) * | 2002-11-21 | 2004-05-26 | Westinghouse Electric Company LLC | Subcritical reactivity measurement method |
| JP2014106104A (en) * | 2012-11-27 | 2014-06-09 | Mitsubishi Heavy Ind Ltd | Subcriticality measuring method and device |
| CN111403058A (en) * | 2020-03-26 | 2020-07-10 | 广西防城港核电有限公司 | Method for measuring control rod value of nuclear reactor |
| WO2020221290A1 (en) * | 2019-04-29 | 2020-11-05 | 岭澳核电有限公司 | Method and device for measuring control rod worth in subcritical state of nuclear power plant |
| CN115331844A (en) * | 2022-09-08 | 2022-11-11 | 中国核动力研究设计院 | Method and system for measuring value of control rod under subcritical condition of nuclear reactor |
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Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP1422723A1 (en) * | 2002-11-21 | 2004-05-26 | Westinghouse Electric Company LLC | Subcritical reactivity measurement method |
| JP2014106104A (en) * | 2012-11-27 | 2014-06-09 | Mitsubishi Heavy Ind Ltd | Subcriticality measuring method and device |
| WO2020221290A1 (en) * | 2019-04-29 | 2020-11-05 | 岭澳核电有限公司 | Method and device for measuring control rod worth in subcritical state of nuclear power plant |
| CN111403058A (en) * | 2020-03-26 | 2020-07-10 | 广西防城港核电有限公司 | Method for measuring control rod value of nuclear reactor |
| CN115331844A (en) * | 2022-09-08 | 2022-11-11 | 中国核动力研究设计院 | Method and system for measuring value of control rod under subcritical condition of nuclear reactor |
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