CN118011462A - Single-point calibration method for off-pile detector under dynamic xenon condition of pressurized water reactor - Google Patents
Single-point calibration method for off-pile detector under dynamic xenon condition of pressurized water reactor Download PDFInfo
- Publication number
- CN118011462A CN118011462A CN202410414992.6A CN202410414992A CN118011462A CN 118011462 A CN118011462 A CN 118011462A CN 202410414992 A CN202410414992 A CN 202410414992A CN 118011462 A CN118011462 A CN 118011462A
- Authority
- CN
- China
- Prior art keywords
- xenon
- dynamic
- condition
- reactor
- under
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 229910052724 xenon Inorganic materials 0.000 title claims abstract description 123
- FHNFHKCVQCLJFQ-UHFFFAOYSA-N xenon atom Chemical compound [Xe] FHNFHKCVQCLJFQ-UHFFFAOYSA-N 0.000 title claims abstract description 123
- 238000000034 method Methods 0.000 title claims abstract description 37
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 22
- 238000004088 simulation Methods 0.000 claims abstract description 20
- 238000005259 measurement Methods 0.000 claims abstract description 10
- 238000004364 calculation method Methods 0.000 claims description 35
- 230000008569 process Effects 0.000 claims description 15
- 230000000694 effects Effects 0.000 claims description 3
- 230000004992 fission Effects 0.000 claims description 3
- 230000004907 flux Effects 0.000 claims description 3
- 230000000630 rising effect Effects 0.000 claims description 2
- 238000012544 monitoring process Methods 0.000 abstract description 2
- 230000008901 benefit Effects 0.000 description 5
- 230000008859 change Effects 0.000 description 2
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
A single point calibration method for an off-pile detector under a dynamic xenon condition of a pressurized water reactor is characterized in that under the dynamic xenon condition that the pressurized water reactor rises to a specified power level, the calibration coefficient of the off-pile detector is determined through a power distribution measured value reconstructed based on a dynamic xenon theoretical library. The method comprises the following steps: firstly, obtaining an in-stack axial power offset measurement value and an out-of-stack detector current signal measurement value under a dynamic xenon condition; secondly, determining an in-stack axial power offset correction factor under the dynamic xenon condition and a response-current correction factor under the dynamic xenon condition; then, numerical simulation is carried out on the moving state of each control rod by adopting reactor core physical analysis software, and an in-reactor axial power offset predicted value and an out-reactor axial power offset predicted value of the moving state of each control rod are obtained; finally, the calibration coefficients of the off-stack detector are determined. The method can directly obtain the calibration coefficient of the off-pile detector under the dynamic xenon condition, is used for monitoring and indicating the power level of the reactor core, and has important industrial application value.
Description
Technical Field
The invention relates to the technical field of pressurized water reactor core physical calculation, in particular to an off-pile detector single-point calibration method under the dynamic xenon condition of a pressurized water reactor.
Background
The commercial pressurized water reactor generally adopts an off-pile detector to monitor the reactor core state during the operation of starting the reactor and raising the power, so that the safety of the pressurized water reactor for raising the power is ensured. However, due to the change of power, the reactor core state indicated by the off-pile detector gradually deviates from a true value, and the off-pile detector needs to be calibrated at the designated power level of 50%, 75%, 100% FP and the like, so that the off-pile detector is ensured to indicate the true power level and the axial power deviation, and the safety and the controllability of the power rise of the reactor are ensured. Traditionally, the single-point calibration implementation condition of the off-pile detector is that the reactor core is required to reach the specified power level and stable for 24 hours to reach the balanced xenon state, and then the single-point calibration can be performed to determine the calibration coefficient of the off-pile detector, so that the waiting time is very time-consuming, and the economy of the nuclear power plant is affected.
Disclosure of Invention
In order to overcome the problems in the prior art, the invention aims to provide a single-point calibration method for an off-pile detector under a dynamic xenon condition of a pressurized water reactor, wherein under the dynamic xenon condition that the power of the pressurized water reactor is increased to a specified power level, the calibration coefficient of the off-pile detector is determined through a power distribution measured value reconstructed by a dynamic xenon theoretical library, so that the waiting time for balancing the xenon condition after the specified power level is reached is effectively reduced; the control rod moving process adopts numerical simulation calculation, so that control rod moving operation in an actual reactor core is avoided, reactor core safety in the calibration of an out-of-pile detector is enhanced, and meanwhile, control rod moving time in the actual reactor core is further reduced.
In order to achieve the above purpose, the invention adopts the following technical scheme:
An off-pile detector single-point calibration method under a pressurized water reactor dynamic xenon condition can determine the calibration coefficient of the off-pile detector through a power distribution measured value reconstructed based on a dynamic xenon theoretical library under the dynamic xenon condition that the pressurized water reactor is started to raise the power to a specified power level; the method comprises the following steps:
Step 1: after the power of the pressurized water reactor is started and increased to a specified power level, acquiring RIC files of a dynamic xenon condition and current signal measured values under the dynamic xenon condition by adopting an off-reactor detector, performing numerical simulation by adopting core physical analysis software to obtain a theoretical library of the dynamic xenon condition, and performing primary core power distribution reconstruction by adopting core power reconstruction software to obtain in-reactor axial power offset measured values under the dynamic xenon condition;
Step 2: performing numerical simulation on the dynamic xenon state of the power increasing process by adopting reactor core physical analysis software to obtain the calculated values of the in-reactor axial power offset under the dynamic xenon condition and the out-of-reactor detector current signal under the dynamic xenon condition, and determining the in-reactor axial power offset correction factor under the dynamic xenon condition and the response-current correction factor under the dynamic xenon condition;
step 3: performing numerical simulation of control rod movement on the basis of a dynamic xenon condition by core physical analysis software, realizing disturbance of axial power distribution, adopting an in-core axial power offset correction factor under the dynamic xenon condition in the step 2 to correct an in-core axial power offset calculation value of each control rod movement state to obtain an in-core axial power offset prediction value of each control rod movement state, and adopting a response-current correction factor under the dynamic xenon condition in the step 2 to correct an out-of-core detector current signal calculation value of each control rod movement state to obtain an out-of-core axial power offset prediction value of each control rod movement state;
Step 4: and (3) performing least square fitting based on the in-stack axial power offset predicted value of each control rod moving state and the out-of-stack axial power offset predicted value of each control rod moving state in the step (3), and determining the out-of-stack detector calibration coefficient.
Preferably, the implementation process of step 1 is as follows:
1) Starting the pressurized water reactor to raise the power to a specified power level, measuring and acquiring RIC files of dynamic xenon conditions by using an in-reactor detector, wherein the RIC files comprise measured values of axial activities of channels of all in-reactor detector components, and acquiring current signal measured values I d,m under the dynamic xenon conditions by using an out-of-reactor detector;
2) Performing numerical simulation calculation on the reactor core state of the dynamic xenon condition in the reactor core physical analysis software to obtain a theoretical library of the dynamic xenon condition, wherein the theoretical library comprises a reactor core three-dimensional power distribution calculation value of the dynamic xenon condition, a U-235 nuclide microscopic fission section of a detector channel and neutron flux density;
3) Based on RIC file of dynamic xenon condition and theoretical library of dynamic xenon condition, core power reconstruction software is adopted to reconstruct power distribution of core once, and in-core axial power offset measurement value under dynamic xenon condition is obtained 。
Preferably, the implementation process of step 2 is as follows:
1) Numerical simulation is carried out on the power rising process from zero power to full power of the reactor core by adopting reactor core physical analysis software, and an in-reactor axial power offset calculated value under the dynamic xenon condition is obtained And an off-stack detector current signal calculation R d,c under dynamic xenon conditions;
2) From in-stack axial power offset measurements under dynamic xenon conditions In-stack axial power offset calculations/>Determining in-stack axial power offset correction factor/>, based on equation 1, under dynamic xenon conditions；
(Equation 1)
3) Determining a response-current correction factor gamma d under the dynamic xenon condition according to a current signal measured value I d,m under the dynamic xenon condition and an off-pile detector current signal calculated value R d,c under the dynamic xenon condition through a formula 2;
(equation 2).
Preferably, the implementation process of step 3 is as follows:
1) Based on the dynamic xenon condition, core physical analysis software is adopted to carry out numerical simulation calculation on the control rod movement, and the in-core axial power offset calculation value of each control rod movement state is obtained And a calculated value R i,c of the off-stack detector current signal for each control rod movement state;
2) In-stack axial power offset correction factor using dynamic xenon conditions In-stack axial power offset calculations/>, for each control rod movement stateCorrection is performed to obtain the in-stack axial power offset prediction value/>, for each control rod movement state, by equation 3；
(Equation 3)
3) Correcting the calculated value R i,c of the current signal of the off-pile detector in the moving state of each control rod by adopting a response-current correction factor gamma d under the dynamic xenon condition, and obtaining the predicted value I i,e of the current signal of the off-pile detector in the moving state of each control rod through a formula 4;
(equation 4)
4) Calculating the out-of-stack axial power offset predicted value of each control rod moving state according to the out-of-stack detector current signal predicted value I i,e of each control rod moving state; The method comprises the following steps: the detector outside the reactor is divided into 2n segments in the axial direction, the sum of the current predicted values of the upper n segments is I i,e,t, the sum of the current predicted values of the lower n segments is I i,e,b, and the power deviation predicted value/>, outside the reactor, of each control rod in the moving state isThe calculation formula expression is shown in formula 5:
(equation 5).
Compared with the prior art, the invention has the following advantages:
1. The method directly carries out the calibration of the detector outside the reactor under the dynamic xenon condition, effectively reduces the waiting time for balancing the xenon condition after reaching the specified power level, and has huge time benefit and economic benefit;
2. according to the invention, only one-time dynamic xenon-conditioned reactor core power distribution measurement is needed, and the control rod moving process adopts numerical simulation calculation, so that the control rod moving operation in the actual reactor core is avoided, the reactor core safety in the out-of-core detector calibration is enhanced, and the control rod moving time in the actual reactor core is further reduced.
3. The correction coefficient of the detector outside the reactor, which is determined by the method, is basically the same as the power level reference value and the axial power deviation reference value respectively, and the calculated power level feedback value and the axial power deviation feedback value can be used for monitoring and indicating the power level of the reactor core and have industrial application value.
Drawings
FIG. 1 is a flow chart of a single point calibration method for a dynamic xenon out-of-pile detector.
Detailed Description
The invention is described in further detail below with reference to the attached drawings and detailed description:
the invention discloses a single-point calibration method of an off-pile detector under a dynamic xenon condition of a pressurized water reactor, which is characterized in that under the dynamic xenon condition that the power of the pressurized water reactor is increased to a specified power level, the calibration coefficient of the off-pile detector is determined only through a power distribution measured value reconstructed by a dynamic xenon theoretical library, and the specific steps are shown in figure 1.
Step 1: after the power of the pressurized water reactor is started and increased to a specified power level, acquiring RIC files of dynamic xenon conditions, acquiring current signal measured values under the dynamic xenon conditions by adopting an off-stack detector, performing numerical simulation by adopting core physical analysis software to acquire a theoretical library of the dynamic xenon conditions, and performing core power distribution reconstruction by adopting core power reconstruction software to acquire in-core axial power offset measured values under the dynamic xenon conditions. This step is mainly subdivided into the following parts:
1) The pressurized water reactor is powered up to a specified power level, such as 50% FP, 75% FP, 100% FP and the like, in the traditional method, the balanced xenon state needs to be achieved by waiting 24 hours, in the embodiment of the invention, only 2 hours need to be waited, at the moment, xenon in the reactor core is still in a dynamic change process, an RIC file for obtaining dynamic xenon conditions is measured by adopting an in-reactor detector, wherein the RIC file comprises measured values of the axial activity of the channels of each in-reactor detector component, and a current signal measured value I d,m under the dynamic xenon condition is obtained by adopting an out-of-reactor detector;
2) Performing numerical simulation calculation on the core state of the dynamic xenon condition by adopting core physical analysis software, such as Simulate program of Studsvik company, SMART program of America, SPARK program of NECP team of Siam traffic university and the like, so as to obtain a theoretical library of the dynamic xenon condition, wherein the theoretical library comprises a core three-dimensional power distribution calculation value, a U-235 nuclide microscopic fission section of a detector channel and neutron flux density;
3) Based on RIC file of dynamic xenon condition and theoretical library of dynamic xenon condition, core power reconstruction software is adopted to reconstruct power distribution of core once, and in-core axial power offset measurement value under dynamic xenon condition is obtained 。
Step 2: numerical simulation is carried out on the dynamic xenon state of the power increasing process by adopting reactor core physical analysis software, so as to obtain the calculated values of the in-reactor axial power offset under the dynamic xenon condition and the out-of-reactor detector current signal under the dynamic xenon condition, and determine the in-reactor axial power offset correction factor under the dynamic xenon condition and the response-current correction factor under the dynamic xenon condition. This step is mainly subdivided into the following parts:
1) Numerical modeling of the power up process of the core from zero to full power using core physics analysis software provides in-core axial power offset calculations under dynamic xenon conditions for specified power levels (e.g., 50%, 75%, and 100%) And an off-stack detector current signal calculation R d,c under dynamic xenon conditions;
2) From in-stack axial power offset measurements under dynamic xenon conditions In-stack axial power offset calculations/>Determining in-stack axial power offset correction factor/>, based on equation 1, under dynamic xenon conditions；
(Equation 1)
3) From the current signal measurement I d,m under dynamic xenon conditions and the off-stack detector current signal calculation R d,c under dynamic xenon conditions, the response-current correction factor γ d under dynamic xenon conditions is determined by equation 2.
(Equation 2)
Step 3: and 2, carrying out numerical simulation on the movement of the control rods on the basis of a dynamic xenon condition by core physical analysis software, realizing disturbance of axial power distribution, adopting an in-core axial power offset correction factor under the dynamic xenon condition in the step 2 to correct the calculated in-core axial power offset value of each control rod movement state to obtain a predicted in-core axial power offset value of each control rod movement state, and adopting a response-current correction factor under the dynamic xenon condition in the step 2 to correct the calculated out-of-core detector current signal value of each control rod movement state to obtain a predicted out-of-core axial power offset value of each control rod movement state. This step is mainly subdivided into the following parts:
1) Based on the dynamic xenon condition, core physical analysis software is adopted to carry out numerical simulation calculation on the movement of the control rod, and 3-6 different control rod positions can be calculated to obtain the in-core axial power offset calculation value of each control rod movement state And a calculated value R i,c of the off-stack detector current signal for each control rod movement state.
2) In-stack axial power offset correction factor using dynamic xenon conditionsIn-stack axial power offset calculations/>, for each control rod movement stateCorrection is performed to obtain the in-stack axial power offset prediction value/>, for each control rod movement state, by equation 3；
(Equation 3)
3) Correcting the calculated value R i,c of the current signal of the off-pile detector in the moving state of each control rod by adopting a response-current correction factor gamma d under the dynamic xenon condition, and obtaining the predicted value I i,e of the current signal of the off-pile detector in the moving state of each control rod through a formula 4;
(equation 4)
4) Obtaining the predicted value of the out-of-pile axial power offset of each control rod moving state according to the predicted value I i,e of the out-of-pile detector current signal of each control rod moving state. The detector outside the reactor is divided into 6 sections in the axial direction, the sum of current predicted values of the upper 3 sections is I i,e,t, the sum of current predicted values of the lower 3 sections is I i,e,b, and the predicted value/>, of the power shift of the outer axial direction of the reactor in the moving state of each control rodThe calculation formula expression is shown in formula 5:
(equation 5)
Step 4: in-stack axial power offset predictions based on each control rod movement state of step 3And out-of-stack axial power offset predictions/>, for each control rod movement stateAnd (3) performing least square fitting, determining the calibration coefficient of the detector outside the pile, and further realizing real-time feedback of the power level and the axial power deviation according to the calibration coefficient.
In this embodiment, the core is arranged with a total of 9 groups of control rods, R, SA, SB, SC, SD, G1, G2, N1, N2, respectively. Except the R bars, the rest control bar groups are all in a full lifting state. The results of the power feedback values calculated from the calibration coefficients obtained under dynamic xenon conditions under different R rod position conditions are shown in Table 1 below, wherein the power reference values were obtained under balanced xenon conditions, and it can be seen that the errors of the power feedback values and the power reference values are very small.
TABLE 1
In this embodiment, the core is arranged with a total of 9 groups of control rods, R, SA, SB, SC, SD, G1, G2, N1, N2, respectively. Except the R bars, the rest control bar groups are all in a full lifting state. The results of the axial power deviation feedback values calculated from the calibration coefficients obtained under dynamic xenon conditions under different R rod position conditions are shown in Table 2 below, wherein the axial power deviation reference values are obtained under balanced xenon conditions, and it can be seen that the errors of the axial power deviation feedback values and the axial power deviation reference values are extremely small.
TABLE 2
In the embodiment, after reaching 73.3% of the power level, the calculation of the calibration coefficients of the off-stack detector is completed after only waiting 2 hours, but the calculation of the calibration coefficients of the off-stack detector can be realized after waiting 24 hours in the traditional method, so that the waiting time for balancing the xenon condition after reaching the specified power level is effectively reduced, and huge time benefit and economic benefit are realized.
Claims (4)
1. An out-of-pile detector single point calibration method under a pressurized water reactor dynamic xenon condition is characterized in that: under the dynamic xenon condition that the pressurized water reactor is started to raise the power to a specified power level, determining the calibration coefficient of the off-pile detector by using the power distribution measured value reconstructed based on the dynamic xenon theoretical library; the method comprises the following steps:
Step 1: after the power of the pressurized water reactor is started and increased to a specified power level, acquiring RIC files of a dynamic xenon condition and current signal measured values under the dynamic xenon condition by adopting an off-reactor detector, performing numerical simulation by adopting core physical analysis software to obtain a theoretical library of the dynamic xenon condition, and performing primary core power distribution reconstruction by adopting core power reconstruction software to obtain in-reactor axial power offset measured values under the dynamic xenon condition;
Step 2: performing numerical simulation on the dynamic xenon state of the power increasing process by adopting reactor core physical analysis software to obtain the calculated values of the in-reactor axial power offset under the dynamic xenon condition and the out-of-reactor detector current signal under the dynamic xenon condition, and determining the in-reactor axial power offset correction factor under the dynamic xenon condition and the response-current correction factor under the dynamic xenon condition;
step 3: performing numerical simulation of control rod movement on the basis of a dynamic xenon condition by core physical analysis software, realizing disturbance of axial power distribution, adopting an in-core axial power offset correction factor under the dynamic xenon condition in the step 2 to correct an in-core axial power offset calculation value of each control rod movement state to obtain an in-core axial power offset prediction value of each control rod movement state, and adopting a response-current correction factor under the dynamic xenon condition in the step 2 to correct an out-of-core detector current signal calculation value of each control rod movement state to obtain an out-of-core axial power offset prediction value of each control rod movement state;
Step 4: and (3) performing least square fitting based on the in-stack axial power offset predicted value of each control rod moving state and the out-of-stack axial power offset predicted value of each control rod moving state in the step (3), and determining the out-of-stack detector calibration coefficient.
2. The method according to claim 1, characterized in that: the implementation process of the step 1 is as follows:
1) Starting the pressurized water reactor to raise the power to a specified power level, measuring and acquiring RIC files of dynamic xenon conditions by using an in-reactor detector, wherein the RIC files comprise measured values of axial activities of channels of all in-reactor detector components, and acquiring current signal measured values I d,m under the dynamic xenon conditions by using an out-of-reactor detector;
2) Performing numerical simulation calculation on the reactor core state of the dynamic xenon condition in the reactor core physical analysis software to obtain a theoretical library of the dynamic xenon condition, wherein the theoretical library comprises a reactor core three-dimensional power distribution calculation value of the dynamic xenon condition, a U-235 nuclide microscopic fission section of a detector channel and neutron flux density;
3) Based on RIC file of dynamic xenon condition and theoretical library of dynamic xenon condition, core power reconstruction software is adopted to reconstruct power distribution of core once, and in-core axial power offset measurement value under dynamic xenon condition is obtained 。
3. The method according to claim 1, characterized in that: the implementation process of the step 2 is as follows:
1) Numerical simulation is carried out on the power rising process from zero power to full power of the reactor core by adopting reactor core physical analysis software, and an in-reactor axial power offset calculated value under the dynamic xenon condition is obtained And an off-stack detector current signal calculation R d,c under dynamic xenon conditions;
2) From in-stack axial power offset measurements under dynamic xenon conditions In-stack axial power offset calculationsDetermining in-stack axial power offset correction factor/>, based on equation 1, under dynamic xenon conditions；
(Equation 1)
3) Determining a response-current correction factor gamma d under the dynamic xenon condition according to a current signal measured value I d,m under the dynamic xenon condition and an off-pile detector current signal calculated value R d,c under the dynamic xenon condition through a formula 2;
(equation 2).
4. The method according to claim 1, characterized in that: the implementation process of the step 3 is as follows:
1) Based on the dynamic xenon condition, core physical analysis software is adopted to carry out numerical simulation calculation on the control rod movement, and the in-core axial power offset calculation value of each control rod movement state is obtained And a calculated value R i,c of the off-stack detector current signal for each control rod movement state;
2) In-stack axial power offset correction factor using dynamic xenon conditions In-stack axial power offset calculations/>, for each control rod movement stateCorrection is performed to obtain the in-stack axial power offset prediction value/>, for each control rod movement state, by equation 3；
(Equation 3)
3) Correcting the calculated value R i,c of the current signal of the off-pile detector in the moving state of each control rod by adopting a response-current correction factor gamma d under the dynamic xenon condition, and obtaining the predicted value I i,e of the current signal of the off-pile detector in the moving state of each control rod through a formula 4;
(equation 4)
4) Calculating the out-of-stack axial power offset predicted value of each control rod moving state according to the out-of-stack detector current signal predicted value I i,e of each control rod moving state; The method comprises the following steps: the detector outside the reactor is divided into 2n segments in the axial direction, the sum of the current predicted values of the upper n segments is I i,e,t, the sum of the current predicted values of the lower n segments is I i,e,b, and the power deviation predicted value/>, outside the reactor, of each control rod in the moving state isThe calculation formula expression is shown in formula 5:
(equation 5).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202410414992.6A CN118011462A (en) | 2024-04-08 | 2024-04-08 | Single-point calibration method for off-pile detector under dynamic xenon condition of pressurized water reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202410414992.6A CN118011462A (en) | 2024-04-08 | 2024-04-08 | Single-point calibration method for off-pile detector under dynamic xenon condition of pressurized water reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN118011462A true CN118011462A (en) | 2024-05-10 |
Family
ID=90954668
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202410414992.6A Pending CN118011462A (en) | 2024-04-08 | 2024-04-08 | Single-point calibration method for off-pile detector under dynamic xenon condition of pressurized water reactor |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN118011462A (en) |
-
2024
- 2024-04-08 CN CN202410414992.6A patent/CN118011462A/en active Pending
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JP5954902B2 (en) | How to monitor the power distribution of a reactor core | |
| KR101158459B1 (en) | Method and installation for monitoring the core of a nuclear reactor | |
| CN101105986A (en) | Reactor reactivity measuring method | |
| CN111737869B (en) | High-precision prediction method for burnup distribution of pressurized water reactor core | |
| KR100991441B1 (en) | Renormalization Method of Excore Neutron Detectors | |
| US6400786B1 (en) | Process and device for monitoring at least one operating parameter of the core of a nuclear reactor | |
| CN107910083A (en) | A kind of nuclear power plant's measurement of rod worth method | |
| CN107863164B (en) | A kind of method of nuclear power plant's out-pile nuclear measurement system design factor calibration | |
| JPS633279B2 (en) | ||
| CN109192341B (en) | Large reactivity measurement method based on three-dimensional space-time dynamics | |
| CN118011462A (en) | Single-point calibration method for off-pile detector under dynamic xenon condition of pressurized water reactor | |
| CN115050496B (en) | Single-point calibration method for external detector of pressurized water reactor | |
| CN110749919A (en) | Method and device for calibrating nuclear reactor out-of-pile detector | |
| JP2008175692A (en) | Measuring method of axial power distribution of core | |
| CN116469589B (en) | Subcritical state rod carving method based on critical rod reaching process | |
| CN115862912B (en) | Method for measuring power distribution of pressurized water reactor core under dynamic xenon condition | |
| JPH0772282A (en) | Method and device for estimating reactor core performance | |
| JP2001133580A (en) | Reactor core performance computing method and apparatus for reactor | |
| CN114596972B (en) | Correction method for shadow effect of control rod of off-stack detector | |
| CN111400869B (en) | Reactor core neutron flux space-time evolution prediction method, device, medium and equipment | |
| Kim et al. | Core simulations using actual detector readings for a Canada deuterium uranium reactor | |
| Li et al. | The development of HOLLY code and single-point ex-core detectors calibration method | |
| CN117558475A (en) | Pressurized water reactor moderator temperature coefficient measuring method based on noise signals | |
| JP3579024B2 (en) | Reactor power monitoring device | |
| KR20230090221A (en) | Method and system for gmdh-based reactor core output prediction |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination |