CN106024078A - Failure diagnosis method for neutron detectors of reactors - Google Patents
Failure diagnosis method for neutron detectors of reactors Download PDFInfo
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- CN106024078A CN106024078A CN201610471993.XA CN201610471993A CN106024078A CN 106024078 A CN106024078 A CN 106024078A CN 201610471993 A CN201610471993 A CN 201610471993A CN 106024078 A CN106024078 A CN 106024078A
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- detector
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- measurement value
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- failure
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Classifications
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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
- G21C17/108—Measuring reactor flux
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/04—Detecting burst slugs
- G21C17/044—Detectors and metering devices for the detection of fission products
- G21C17/047—Detection and metering circuits
-
- 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
-
- 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 a failure diagnosis method for neutron detectors of reactors. The failure of measured values of the detectors is diagnosed at three stages with a direct comparison method, an inter-measured-value comparison method and a measured value and responding reconstructed value comparison method for the measured values of the detectors; due to the combination of the three judging method, the failure diagnosis method for the reactors can effectively diagnose the complete failure of the detectors, can make accurate diagnosis for the deviation failure of the measured values of the detectors from normal values and has the capacity of distinguishing the detector failure from the local power oscillation; by removing the measured values of the failed detectors, the measured values of the failed detectors are not used by an online monitoring system for reactor core power distribution, and reliable input parameters are provided for the online monitoring system. The failure diagnosis method for the detectors is not limited by the type of the detectors, an online monitoring method and the failure type of the detectors, and has the advantages that the failure diagnosis time is short, the diagnosis is quick, and diagnosed results are accurate and reliable.
Description
Technical field
The present invention relates to nuclear reactor run and security technology area, be specifically related to a kind of diagnostic reaction pile neutron and visit
Survey the method that device lost efficacy.
Background technology
In order to ensure safe, the economic benefit of raising reactor of reactor core, need reactor core power is divided
Cloth carries out on-line monitoring.I.e. reactor capability distribution is carried out time and continuous monitoring spatially.Owing to power distribution is difficult to
Directly monitoring, nuclear power plant typically carrys out indirect monitoring heap internal power by monitoring heap in-core netron-flux density and is distributed.
Most reactors are furnished with neutron measurement system (heap internally-fixed detector or packaged type detector) in heap, in order to
Netron-flux density in monitoring heap;Also responding heap utilizes out-pile neutron measurement system (out-pile neutron detector) to realize in heap
The monitoring of neutron flux.Be compared to that ex-core detector measuring point is few, precision relatively low easily by can in the feature of external disturbance and heap
Movin gdetector can not provide the feature of metrical information continuously, and heap internally-fixed detector is with its higher precision and measures letter
The features such as the seriality of breath are increasingly widely applied, and are used in reactor capability distribution on-line monitoring.
The true and accurate of detector measurement value has important impact for core power distribution on-line monitoring.And detector
Inefficacy be the situation often occurred in a class reactor, especially for heap internally-fixed detector, it is in height for a long time
Under radiation parameter, failure probability increases.Therefore, detector measurement value is being utilized to carry out three-dimensional core power distribution on-line monitoring meter
During calculation, the failure diagnosis carrying out detector is the most necessary.
Detector failure of removal typically has following a few class: complete failure, i.e. detector non-metering;Droop lost efficacy, i.e.
Failure detection device measured value and normal value have the deviation of a fixed constant;Signal drift, i.e. detector measurement value has with normal value
One deviation changed linearly over time;Precise decreasing, i.e. measured value variance within the specific limits changes.Currently for heap
Core power is distributed in line monitoring system, and detector measurement value is as its input signal, and systems most is with for input signal
Self-checking function, but respond when this detection is typically only capable to for detector generation complete failure, and detection can not be detected
There is other kinds of inefficacy in device.Accordingly, it would be desirable to the method that the diagnostic processor inventing a kind of fast and reliable lost efficacy.
Summary of the invention
For the problem overcoming above-mentioned prior art to exist, it is an object of the invention to provide a kind of diagnostic reaction pile neutron
The method that detector lost efficacy, is applied to during core power on-line monitoring calculates, compares by directly comparing, between measured value and survey
Value compares triphasic judgement with reconstruction value, enables whether on-line monitoring system diagnostic processor measured value rapidly exists
Abnormal, and ensure not use in on-line monitoring system and be diagnosed to be abnormal detector measurement value.
To achieve these goals, present invention employs techniques below scheme to be practiced:
A kind of method that diagnostic reaction pile neutron detector lost efficacy, comprises the steps:
Step 1: read reactor core physical dimension, reactor core material layout, detector total number, probe access number
Mesh, detector title;
Step 2: read neutron detector measured value and detector position at the neutron detector of reactor in-core;Root
According to detector total number in step 1, it is judged that whether detector measurement value number is equal to detector total number, if being equal to, under carrying out
One step;If being not equal to, then basis does not reads the detector position of detector measurement value, determines failure detection device title;
Step 3: according to the detector measurement value read in step 2, it is judged that whether each measured value is 0 value or negative value,
If 0 value or negative value, then remove this value;Obtain one group of detector measurement value removing 0 value or negative value, be referred to as, lost efficacy for the first time
Detector measurement value after diagnosis;
Step 4: on the basis of detector measurement value in step 3, it is judged that whether each detector measurement value is beyond institute
There are M times or 1/M times of meansigma methods of measured value, wherein M > 1, if exceeding, then removing this value;Obtain one group to remove beyond all surveys
Meansigma methods M times of value or the detector measurement value of 1/M times, be referred to as, the detector measurement value after failure diagnosis for the second time;M's
Selection is the most different, by User Defined according to different reactor core types, different type photodetectors;
Step 5: according to reading in reactor core geometry, reactor core material layout ginseng in the detector measurement value in step 4 and step 1
Number, carries out core power and is distributed online monitoring calculation and the calculating of explorer response reconstruction value;
Step 6: be distributed online monitoring calculation result according to core power in step 5, obtains one group of explorer response reconstruct
The detector measurement value of gained in value integrating step 3, carries out detector measurement value and reconstruction value to the detector of all positions
Relative error calculates;Computing formula is:
Step 7: according to the relative error of all detector positions of step 6 gained, it is judged that explorer response reconstruction value and spy
Whether survey device measured value relative error more than N%, wherein N > 10, if being more than, then remove this detector measurement value;Obtain one group to go
Fall explorer response reconstruction value and the detector measurement value relative error detector measurement value more than N%, be referred to as, through the 3rd
Detector measurement value after secondary failure diagnosis;The value of N and heap-type, type photodetector are relevant, by User Defined;
Step 8: according to the detector measurement value obtained in step 7, again carry out the calculating of step 5, step 6, step 7,
Until new failure detection device no longer occurs in the judgement of step 7;
Step 9: be distributed online monitoring calculation knot according to step 8, output detector failure diagnosis result, and core power
Really, explorer response value result of calculation.
Compared with prior art, the present invention has a following outstanding advantages:
1. detector failure diagnosis provides for reactor core power distribution on-line monitoring and inputs parameter reliably, not only may be used
To be diagnosed to be detector complete failure fault, it is also possible to be diagnosed to be the inefficacy of detector deviation normal value.
2. combine core power and be distributed in line monitoring system, failure detection device measured value is correctly processed, it is ensured that heap
Core on-line monitoring system does not use fault detector measured value to carry out the reconstruct of power distribution.
3., for detector failure diagnosis with self-checking function, detector can be distinguished and lost efficacy and reactor core partial power
Reduce or rise high operation characteristic.
4. the detector failure diagnosis used time is short, and diagnosis rapidly, is distributed in line monitoring system for core power and realizes prison in real time
Survey provides safeguard.
Accompanying drawing explanation
Fig. 1 is detector failure diagnosis flow chart.
Fig. 2 is that core power is distributed in line monitoring system flow chart.
Fig. 3 is harmonic expansion method on-line monitoring flow chart.
Detector measurement value when Fig. 4 is axial 10th detector inefficacy.
Detector measurement value and reconstruction value when Fig. 5 is axial 10th detector inefficacy.
Fig. 6 is that the axial partial power of reactor core reduces detector measurement value.
Detailed description of the invention
Detector failure diagnosis flow chart is as shown in Figure 1.As it can be seen, the diagnosis process that detector lost efficacy not only occurs on
Core power is distributed before online monitoring calculation, i.e. the most directly judges detector measurement value, compares, for online between measured value
Monitoring provides reliable input signal;During also occurring in on-line monitoring calculating, i.e. measured value compares with reconstruction value, by detector
Failure diagnosis calculates mutual iteration with the distribution of on-line reorganization power to be carried out, and examines during the diagnosis losing efficacy detector the most simultaneously
Consider the contact between prml detector measured value so that detector failure diagnosis lost efficacy and reactor core local merit with distinguishing detector
The function of rate vibration.
Specific implementation method includes following aspect:
1. read reactor core physical dimension, reactor core material layout, detector total number, probe access number, spy
Survey device title;
2. at the neutron detector of reactor in-core, read detector measurement value and neutron detector position;According to step
Detector total number in rapid 1, it is judged that detector measurement value number, whether equal to detector total number, if being equal to, carries out next step;
If being not equal to, then basis does not reads the detector position of detector measurement value, determines failure detection device title.
3., according to step 2 is read in data, detector measurement value is carried out failure diagnosis for the first time, each detector is surveyed
Value does individually judgement, it is judged that whether detector measurement value is 0 or negative value, owing in heap, neutron detector is to lead to neutron in heap
Amount responds, thus without 0 value or negative value occur;If 0 value or the situation of negative value, then this position of system automatic rejection occurs
Detector measurement information, obtain the detector measurement value after first time failure diagnosis.
The most in step 3 on the basis of gained detector measurement value, detector measurement value is carried out second time failure diagnosis, enters
Compare between row measured value, it is judged that whether detector measurement value is beyond average value measured M times or 1/M times, and wherein M > 1, due in heap
Neutron flux is in certain scope, in therefore detector measurement value also should be at certain scope, seriously beyond meansigma methods
(excessive or too small) all can determine that and lost efficacy into detector.If occurring beyond meansigma methods M times or the detector measurement value of 1/M times, then
Remove this value, obtain the detector measurement value after second time failure diagnosis.M selects according to different reactor core type, different spies
Survey device type the most different, by User Defined.
5., according to the reactor core geometry read in gained detector measurement value in step 4 and step 1 and material arrangement parameter, enter
Row core power is distributed online monitoring calculation and explorer response reconstruction value calculates.
6. according to step 5 gained explorer response reconstruction value, and gained detector measurement value in step 3, to all spies
Surveying device position and carry out the relative error calculating of detector measurement value and reconstruction value, computing formula is:
7., according to step 6 gained detector measurement value and reconstruction value relative error, detector measurement value is carried out third time
Failure diagnosis, measures the comparison of value and reconstruction value, it is judged that detector measurement value and the detection obtained after once reconstruct
Device reconstruction value relative error, whether more than N%, wherein, N > 10, if there is the situation that relative error is excessive, then rejects this position
Detector measurement value, obtain the detector measurement value after third time failure diagnosis.The value of N and heap-type, detector class
Type is relevant, can be by User Defined.
8. according to the effective detector measurement value obtained in step 7, again carry out step 5, step 6, step 7, calculating,
Until new failure detection device no longer occurs in the judgement of step 7;
9. according to step 8, output detector failure diagnosis result after all detector failure diagnosis steps, and adopt
It is distributed online monitoring calculation result, the calculating of explorer response value with the core power after eliminating all failure detection device measured values
Result.
In the present invention, detector placement information in reactor core is read in by step 1, according to the detection read in step 1
Detector measurement value in step 2 is done preliminary judgement by device positional information, obtains the detection not having return detector measured value
Device position.
Measured value after the first time failure diagnosis obtained in step 3 is unreasonable for eliminating on the basis of initial measurement
0 value or negative value after measured value.Measured value after the second time failure diagnosis obtained in step 4 is after diagnosis for the first time
On the basis of measured value, remove the serious measured value beyond average value measured and obtain.In judge process, if reactor core generation heap in certain
The power of position quickly raises, and the most now the detector measurement value near this position also can the most quickly raise, even beyond visiting
Survey device average value measured.For preventing from producing the erroneous judgement losing efficacy detector in the case, the present invention proposes and to detector is
The secondary diagnostic method of no inefficacy, the most in step 6, the detector measurement value for comparing with detector reconstruction value is in step
Measured value after the first time failure diagnosis obtained in 3.Such purpose is, utilizes and is distributed on-line monitoring through core power
The explorer response reconstruction value obtained after calculating, is determined, to second time failure diagnosis in step 4, the detector failed and carries out
Failure diagnosis again, if now reconstruction value is the biggest with the error of measured value, then can finally judge this position sensor
Lost efficacy, if now reconstruction value is the least with measurement error, although then can determine whether that the detector measurement value of this position is flat beyond measuring
Average is more than M times or 1/M times, but this detector did not lose efficacy, but reflects the truth of reactor core.
Present invention core power in steps of 5 is distributed the calculating of online monitoring calculation and explorer response reconstruction value and can use
Core power the most reliable, quick is distributed in line monitoring method, such as harmonic expansion method, simulated calibration method, coefficient of coup method,
Method of least square, erro synthesis, internal boundary condition method, the present invention for the method for detector failure diagnosis not by reactor core merit
Rate is distributed in the restriction of line monitoring method.General core power is distributed in the flow chart of line monitoring system as shown in Figure 2.With harmonic wave
As a example by the method for development, on-line monitoring system flow chart based on harmonic expansion method is as shown in Figure 3.
Step 8 is the iterative cycles for step 5 to step 7, and step 7 retrieves " failure diagnosis for the third time each time
After detector measurement value " be intended to re-start an on-line monitoring and calculate and re-start " for the third time " failure diagnosis, until
No longer there is new failure detection device to be diagnosed and just think that this diagnosis process terminates.
The present invention passes through the three phases judgement to detector measurement value, it is achieved whether detector measurement value is existed exception
Diagnosis rapidly, and ensure not use in on-line monitoring system and be diagnosed to be abnormal detector measurement value.
For checking effectiveness of the invention, use typical case's pressurized water reactor core structural exploration device inefficacy example.Assume in reactor core
There is inefficacy as shown in Figure 4 in axial 10th detector of probe access, then uses general detector failure diagnosis mode
This detector cannot be diagnosed lost efficacy, it is necessary to this detector measurement value together considered with other detector measurement values being adjacent
Just can be diagnosed to be this detector and there is obvious failure characteristics.Result shows, uses the present invention to carry out detector failure diagnosis, at this
In reactor core example, selecting M=20, N=30, the inefficacy of this structure is diagnosed to be exactly.Further, failure detection device is being weeded out
The explorer response reconstruction value obtained after the distribution reconstruct of information laggard row core power is as shown in Figure 5.The visible present invention has very
High computational accuracy and judgment accuracy.
Losing efficacy and the separating capacity of local power oscillations for reactor core detector for the checking present invention, design is as shown in Figure 6
Example, dotted line for assume reactor core occur partial power reduce time detector measurement value.The application present invention carries out detector inefficacy
Diagnosis, then do not have detector to be diagnosed as losing efficacy.Result shows, the present invention is when carrying out detector failure diagnosis in application, will not be by
Reactor core occurs the operating mode of the reading deviation normal value of the detector that causes of local power oscillations to be mistaken for detector to lose efficacy.This is described
Invent the diagnostic result that detector was lost efficacy accurately and reliably.
The present invention, in terms of detector failure diagnosis, is not distributed online monitoring calculation side by type photodetector, core power
Method, failure type limit, and have reliable precision and the highest efficiency, adapt to the calculating requirement in engineering reality.
Claims (1)
1. the method that a diagnostic reaction pile neutron detector lost efficacy, it is characterised in that: comprise the steps:
Step 1: read reactor core physical dimension, reactor core material layout, detector total number, probe access number, spy
Survey device title;
Step 2: read neutron detector measured value and detector position at the neutron detector of reactor in-core;According to step
Detector total number in rapid 1, it is judged that detector measurement value number, whether equal to detector total number, if being equal to, carries out next step;
If being not equal to, then basis does not reads the detector position of detector measurement value, determines failure detection device title;
Step 3: according to the detector measurement value read in step 2, it is judged that whether each measured value is 0 value or negative value, if 0
Value or negative value, then remove this value;Obtain one group of detector measurement value removing 0 value or negative value, be referred to as, for the first time after failure diagnosis
Detector measurement value;
Step 4: on the basis of detector measurement value in step 3, it is judged that whether each detector measurement value is beyond all surveys
M times or 1/M times of the meansigma methods of value, wherein M > 1, if exceeding, then removes this value;Obtain one group to remove beyond all measured values
Meansigma methods M times or the detector measurement value of 1/M times, be referred to as, the detector measurement value after failure diagnosis for the second time;The selection of M
The most different, by User Defined according to different reactor core types, different type photodetectors;
Step 5: according to reading in reactor core geometry, reactor core material arrangement parameter in the detector measurement value in step 4 and step 1, enter
Row core power is distributed online monitoring calculation and explorer response reconstruction value calculates;
Step 6: be distributed online monitoring calculation result according to core power in step 5 and obtain one group of explorer response reconstruction value, knot
Close the detector measurement value of gained in step 3, the detector of all positions is carried out detector measurement value relative with reconstruction value
Error Calculation;Computing formula is:
Step 7: according to the relative error of all detector positions of step 6 gained, it is judged that explorer response reconstruction value and detector
Whether measured value relative error is more than N%, wherein N > 10, if being more than, then remove this detector measurement value;Obtain one group to eliminate
Explorer response reconstruction value and the detector measurement value relative error detector measurement value more than N%, is referred to as, loses through third time
Detector measurement value after effect diagnosis;The value of N and heap-type, type photodetector are relevant, by User Defined;
Step 8: according to the detector measurement value obtained in step 7, again carry out the calculating of step 5, step 6, step 7, until
New failure detection device no longer occurs in the judgement of step 7;
Step 9: according to step 8, output detector failure diagnosis result, and core power distribution online monitoring calculation result, spy
Survey device response value result of calculation.
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Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN107316665A (en) * | 2017-06-01 | 2017-11-03 | 西安交通大学 | A kind of Optimization Design of self-power neutron detector structure |
CN109887625A (en) * | 2019-03-07 | 2019-06-14 | 中国核动力研究设计院 | Detector failure countermeasure and electric current restoration methods for reactor core on-line monitoring |
CN111566515A (en) * | 2018-01-05 | 2020-08-21 | 韩国水力原子力株式会社 | Fault monitoring method of neutron high-power detector |
TWI773001B (en) * | 2019-12-06 | 2022-08-01 | 美商西屋電器公司 | Method and apparatus employing vanadium neutron detectors |
Citations (12)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS59180480A (en) * | 1983-03-31 | 1984-10-13 | Toshiba Corp | Fault detector for neutron detector |
US4517468A (en) * | 1984-04-30 | 1985-05-14 | Westinghouse Electric Corp. | Diagnostic system and method |
US6236698B1 (en) * | 1998-03-17 | 2001-05-22 | Kabushiki Kaisha Toshiba | Nuclear reactor power distribution monitoring system and method including nuclear reactor instrumentation system |
JP2006250802A (en) * | 2005-03-11 | 2006-09-21 | Toshiba Corp | Power distribution monitoring device and its monitoring method |
JP2008275358A (en) * | 2007-04-26 | 2008-11-13 | Toshiba Corp | Device and method for detecting damage in nuclear reactor |
CN101399091A (en) * | 2008-11-07 | 2009-04-01 | 西安交通大学 | Method for on-line monitoring neutron flux distribution of nuclear reactor core |
CN102682862A (en) * | 2012-05-25 | 2012-09-19 | 中国核动力研究设计院 | Online diagnosis method for effectiveness states of thermocouples of reactor core of pressurized water reactor nuclear power plant |
CN103150424A (en) * | 2013-02-05 | 2013-06-12 | 西安交通大学 | Method for acquiring fine distribution of reactor core three dimensional neutron flux density of reactor |
CN103218512A (en) * | 2013-03-14 | 2013-07-24 | 西安交通大学 | Method for acquiring neutron angular flux density in nuclear fuel assembly |
CN103294899A (en) * | 2013-05-10 | 2013-09-11 | 西安交通大学 | Method for calculating core neutron flux distribution of small experimental reactor |
CN105044759A (en) * | 2015-07-29 | 2015-11-11 | 中国船舶重工集团公司第七一九研究所 | Digital nuclear detector state evaluation and guarantee maintenance method and system |
JP2016045191A (en) * | 2014-08-25 | 2016-04-04 | コリア、ハイドロ、アンド、ニュークリア、パワー、カンパニー、リミテッドKorea Hydro & Nuclear Power Co.,Ltd. | Multiple thermocouple furnace inner core measuring instrument, and nuclear reactor internal state monitoring system and monitoring method after serious accident using the same |
-
2016
- 2016-06-24 CN CN201610471993.XA patent/CN106024078B/en active Active
Patent Citations (12)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS59180480A (en) * | 1983-03-31 | 1984-10-13 | Toshiba Corp | Fault detector for neutron detector |
US4517468A (en) * | 1984-04-30 | 1985-05-14 | Westinghouse Electric Corp. | Diagnostic system and method |
US6236698B1 (en) * | 1998-03-17 | 2001-05-22 | Kabushiki Kaisha Toshiba | Nuclear reactor power distribution monitoring system and method including nuclear reactor instrumentation system |
JP2006250802A (en) * | 2005-03-11 | 2006-09-21 | Toshiba Corp | Power distribution monitoring device and its monitoring method |
JP2008275358A (en) * | 2007-04-26 | 2008-11-13 | Toshiba Corp | Device and method for detecting damage in nuclear reactor |
CN101399091A (en) * | 2008-11-07 | 2009-04-01 | 西安交通大学 | Method for on-line monitoring neutron flux distribution of nuclear reactor core |
CN102682862A (en) * | 2012-05-25 | 2012-09-19 | 中国核动力研究设计院 | Online diagnosis method for effectiveness states of thermocouples of reactor core of pressurized water reactor nuclear power plant |
CN103150424A (en) * | 2013-02-05 | 2013-06-12 | 西安交通大学 | Method for acquiring fine distribution of reactor core three dimensional neutron flux density of reactor |
CN103218512A (en) * | 2013-03-14 | 2013-07-24 | 西安交通大学 | Method for acquiring neutron angular flux density in nuclear fuel assembly |
CN103294899A (en) * | 2013-05-10 | 2013-09-11 | 西安交通大学 | Method for calculating core neutron flux distribution of small experimental reactor |
JP2016045191A (en) * | 2014-08-25 | 2016-04-04 | コリア、ハイドロ、アンド、ニュークリア、パワー、カンパニー、リミテッドKorea Hydro & Nuclear Power Co.,Ltd. | Multiple thermocouple furnace inner core measuring instrument, and nuclear reactor internal state monitoring system and monitoring method after serious accident using the same |
CN105044759A (en) * | 2015-07-29 | 2015-11-11 | 中国船舶重工集团公司第七一九研究所 | Digital nuclear detector state evaluation and guarantee maintenance method and system |
Cited By (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN107316665A (en) * | 2017-06-01 | 2017-11-03 | 西安交通大学 | A kind of Optimization Design of self-power neutron detector structure |
CN111566515A (en) * | 2018-01-05 | 2020-08-21 | 韩国水力原子力株式会社 | Fault monitoring method of neutron high-power detector |
CN111566515B (en) * | 2018-01-05 | 2023-10-13 | 韩国水力原子力株式会社 | Fault monitoring method for neutron high-power detector |
CN109887625A (en) * | 2019-03-07 | 2019-06-14 | 中国核动力研究设计院 | Detector failure countermeasure and electric current restoration methods for reactor core on-line monitoring |
CN109887625B (en) * | 2019-03-07 | 2022-04-22 | 中国核动力研究设计院 | Detector failure coping method and current recovery method for reactor core online monitoring |
TWI773001B (en) * | 2019-12-06 | 2022-08-01 | 美商西屋電器公司 | Method and apparatus employing vanadium neutron detectors |
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