CN107644695A - One kind is based on16The method at the steady peak and power measurement of N fuel element rupture detection - Google Patents
One kind is based on16The method at the steady peak and power measurement of N fuel element rupture detection Download PDFInfo
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- CN107644695A CN107644695A CN201710964579.7A CN201710964579A CN107644695A CN 107644695 A CN107644695 A CN 107644695A CN 201710964579 A CN201710964579 A CN 201710964579A CN 107644695 A CN107644695 A CN 107644695A
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- reactor
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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
The invention discloses one kind to be based on16The method at the steady peak and power measurement of N fuel element rupture detection, bypass circulation is set in reactor-loop system, will be contained16N cooling agent is drawn from primary Ioops, and flows through damage monitoring system by pipeline, is then back to primary Ioops system；When the valve of bypass circulation is opened, using in fuel element rupture detection systematic survey cooling agent16N, measure road location D corresponding to peak position1,16Road location D corresponding to N characteristic peaks2, peak position shifted by delta D=D1‑D2, measurement amendments of the peak position shifted by delta D for steady peak or detector；Using heat output of reactor measuring system to reactor capability and16N is demarcated, formed power and16Corresponding relation between N, after completing demarcation, pass through measurement16N level of activitys obtain the power of reactor.The present invention in major loop by drawing cooling agent, by cooling agent16N is used for the steady peak of fuel element rupture detection detection, so as to cancel outer radioactive source, can also be used for the monitoring of reactor capability in addition.
Description
Technical field
The present invention relates to the fuel element rupture detection technology of nuclear reactor, and in particular to one kind is based on16N fuel element
The method at the steady peak and power measurement of breakage monitoring.
Background technology
Can is first of barrier for preventing radioactive fission product from leaking out, if fuel element occurs
Breakage, the fission product in fuel element will be discharged into primary Ioops cooling agent.Reactor must be provided with fuel element failure
Monitoring system, so as to find the breakage of fuel element in time, and take measures when necessary, so that it is guaranteed that the peace of reactor
Entirely.
In nuclear reactor fuel element breakage monitoring, nuclear detector by environment temperature due to being influenceed, photomultiplier
Gain and the luminous efficiency etc. of crystal can all change, so as to which the gamma spectrum for causing system Nuclear Instrument to export drifts about,
This just needs to take peak stabilizing technique.More conventional steady peak method is to quote a radioactive reference source in pipeline external to be at present
Standard, when peak position is drifted about, by analyzing the peak position of reference source to correct measuring system, so that corresponding gamma energy is penetrated
The output pulse amplitude of line is constant.More conventional reference source includes at present241Am、137Cs and60Co etc., these reference sources can
Relatively accurately obtain peak position information.
For whole Nuclear Detection System, the use of radioactive reference source, it on the one hand can increase the radiation of staff
Dosage, on the other hand radioactive source risk out of control all be present in links such as equipment generation, transports.
The content of the invention
The technical problems to be solved by the invention are the uses of radioactive reference source for whole Nuclear Detection System,
On the one hand the dose of radiation of staff can be increased, on the other hand radioactive source all be present in links such as equipment generation, transports
Risk out of control, its object is to provide one kind to be based on16The method at the steady peak and power measurement of N fuel element rupture detection, should
Method cancels outer radioactive source, by standard source caused by nuclear reactor self-operating16N is used for the steady peak of nuclear detector, reduces work
The dose of radiation of personnel, it also ensure that the safety of the links such as equipment generation, transport.
The present invention is achieved through the following technical solutions：
One kind is based on16The method at the steady peak and power measurement of N fuel element rupture detection, comprises the following steps：
(1) bypass circulation is introduced coolant into：Bypass circulation is set in reactor-loop system, will be contained16N's is cold
But agent is drawn from primary Ioops, and flows through damage monitoring system by pipeline, is then back to primary Ioops system；
(2) when the valve of the bypass circulation in step (1) is opened, coolant flow is through bypass circulation, using fuel element
In damage monitoring system measurement cooling agent16N, measure road location D corresponding to peak position1,16Road location D corresponding to N characteristic peaks2, peak position is inclined
Move Δ D=D1-D2, measurement amendments of the peak position shifted by delta D for steady peak or detector；
(3) when the valve of the bypass circulation in step (1) is opened, coolant flow is through bypass circulation, using reactor heat
Power measuring system to reactor capability and16N is demarcated, formed power and16Corresponding relation between N, after completing demarcation,
Pass through measurement16N level of activitys obtain the power of reactor.
At present in nuclear reactor fuel element breakage monitoring, nuclear detector due to being influenceed by factors such as environment temperatures,
The gain of photomultiplier and the luminous efficiency of crystal etc. can all change, so as to cause the gamma spectrum that system Nuclear Instrument exports
Drift about, this just needs to take peak stabilizing technique.More conventional steady peak method is to quote a radiation in pipeline external at present
Property reference source be standard, when peak position is drifted about, by analyzing the peak position of reference source to correct measuring system, so that right
Answer the output pulse amplitude of gamma energy ray constant.And reference source more conventional at present includes241Am、137Cs and60Co etc. is this kind of
The reference source of high radioactivity, these reference sources can relatively accurately obtain peak position information.But it is directed to whole Nuclear Detection System
For, it the use of radioactive reference source, on the one hand can increase the dose of radiation of staff, on the other hand produce in equipment, fortune
It is defeated to wait links radioactive source risk out of control to be all present.The fuel element rupture detection system being related to during steady peak is existing
System, it is also prior art to radioactivity survey in cooling agent, is contained in the cooling agent actually after breakage16N, still
Those skilled in the art do not expect utilizing at present16N carries out steady peak, and it is thought16N belongs to interference nucleic, utilizes in history
Need to be eliminated as much as during total γ detections16N influences to caused by result of detection, therefore can be excluded automatically utilizing16N is disturbed
Spectrometer when just do not consider utilize it due to inertial thinking, while built in usinging the steady peak of radiation source progress method suitable for one
As situation, and the situation handled by this programme is special object, is added16N is not the characteristic nuclide of damaged diagnosis, therefore easily
By instrument development, personnel ignore, and the conventional method of continuing to use of meeting inertia selects steady peak mode.The present invention in major loop by drawing
Go out cooling agent, existing in cooling agent in itself16N is used for the steady peak of fuel element rupture detection detection, so as to cancel outer radiation
Source, reduce the dose of radiation of staff, also ensure that the safety of the links such as equipment generation, transport, while also will not
Steady peak effect is influenceed because of the error of outer radioactive source, the process at steady peak can also ensure that peak value is accurate, can also be used in addition
The monitoring of reactor capability, according to after demarcation formed power and16Corresponding relation between N, after completing demarcation, pass through measurement16N
Level of activity obtains the power of reactor.
The principle at steady peak：The γ spectral peaks measured in gamma ray spectrometer long-time use can drift about, and main cause includes：Environment
The influence of temperature, the fatigue effect of component, aging phenomenon etc..To reduce the influence of γ spectral peaks drift, known peak can be used
The radiation source (standard source) of value carries out steady peak, i.e., using spectrometer measurement standard source, if the peak value of measurement result and standard source has
Deviation, then adjust supply voltage etc. so that measurement result is consistent with the peak value of standard source.
For the ease of operational control, bypass circulation is provided with valve, valve is opened at steady peak or measurement reactor capability
Door forms the connection with main pipeline, does not carry out closing valve cut-out bypass circulation and supervisor when steady peak or measurement reactor capability
The connection in road, is controlled according to use state, ensure that the cooling agent in bypass circulation is in real-time status, realizes online
Steady peak and measurement in real time.
The present invention compared with prior art, has the following advantages and advantages：The present invention in major loop by drawing
Go out cooling agent, by cooling agent16N is used for the steady peak of fuel element rupture detection detection, so as to cancel outer radioactive source, in addition
Available for the monitoring of reactor capability, the dose of radiation of staff is which reduced, also ensure that equipment generation, transport etc. are each
The safety of link.
Brief description of the drawings
Accompanying drawing described herein is used for providing further understanding the embodiment of the present invention, forms one of the application
Point, do not form the restriction to the embodiment of the present invention.In the accompanying drawings：
Fig. 1 is the workflow schematic diagram of the present invention.
Mark and corresponding parts title in accompanying drawing：
1- main pipelines, 2- valves, 3- bypass circulations, 4- detectors.
Embodiment
For the object, technical solutions and advantages of the present invention are more clearly understood, with reference to embodiment and accompanying drawing, to this
Invention is described in further detail, and exemplary embodiment of the invention and its explanation are only used for explaining the present invention, do not make
For limitation of the invention.
Embodiment：
As shown in figure 1, one kind is based on16The method at the steady peak and power measurement of N fuel element rupture detection, including it is following
Step：
(1) bypass circulation is introduced coolant into：Bypass circulation is set below main pipeline 1 in reactor-loop system
3, and the both ends of bypass circulation 3 connect with main pipeline 1 respectively, will contain16N cooling agent is drawn from primary Ioops, and passes through pipe
Road flows through damage monitoring system, is then back to primary Ioops system, due to16N half-life period is very short, stream of the cooling agent in bypass line 3
The dynamic time should be as far as possible short.Bypass circulation 3 set two valves 2, steady peak or measurement reactor capability when open valve 2 formed with
The cut-out of valve 2 and the connection of main pipeline are closed after the completion of the connection of main pipeline 1, steady peak or measurement reactor capability, ensures cooling
The on-line measurement of agent measurement；
(2) when the valve of the bypass circulation in step (1) is opened, coolant flow is through bypass circulation, using fuel element
In damage monitoring system measurement cooling agent16N, measure road location D corresponding to peak position1,16Road location D corresponding to N characteristic peaks2, peak position is inclined
Move Δ D=D1-D2, peak position shifted by delta D can be used to the measurement amendment at steady peak or detector 4；
(3) when the valve of the bypass circulation in step (1) is opened, coolant flow is through bypass circulation, using reactor heat
Power measuring system to reactor capability and16N is demarcated, formed power and16Corresponding relation between N, after completing demarcation,
Measurement can be passed through16N level of activitys obtain the power of reactor.
The present invention is applied to the steady peak of nuclear reactor fuel element breakage monitoring detector and the measure to reactor capability,
It utilizes radionuclide caused by reactor self-operating16N, will16N uses as standard source for fuel element rupture detection
The steady peak of detector, so as to cancel the outer radioactive source for the steady peak of detector, while cooling agent is drawn from primary Ioops system, flowed through
Damage monitoring system, primary Ioops system is then back to, the waste and stop of cooling agent will not be caused, by primary Ioops cooling agent
In16N level of activity measures reactor capability, has the function of power measurement concurrently while steady peak.
Above-described embodiment, the purpose of the present invention, technical scheme and beneficial effect are carried out further
Describe in detail, should be understood that the embodiment that the foregoing is only the present invention, be not intended to limit the present invention
Protection domain, within the spirit and principles of the invention, any modification, equivalent substitution and improvements done etc., all should include
Within protection scope of the present invention.
Claims (2)
1. one kind is based on16The method at the steady peak and power measurement of N fuel element rupture detection, it is characterised in that including following
Step：
(1) bypass circulation is introduced coolant into：Bypass circulation is set in reactor-loop system, will be contained16N cooling agent
Drawn from primary Ioops, and damage monitoring system is flowed through by pipeline, be then back to primary Ioops system；
(2) when the valve of the bypass circulation in step (1) is opened, coolant flow is through bypass circulation, using fuel element failure
In monitoring system measurement cooling agent16N, measure road location D corresponding to peak position1,16Road location D corresponding to N characteristic peaks2, peak position shifted by delta
D=D1-D2, measurement amendments of the peak position shifted by delta D for steady peak or detector；
(3) when the valve of the bypass circulation in step (1) is opened, coolant flow is through bypass circulation, using heat output of reactor
Measuring system to reactor capability and16N is demarcated, formed power and16Corresponding relation between N, after completing demarcation, pass through
Measurement16N level of activitys obtain the power of reactor.
2. one kind according to claim 1 is based on16The method at the steady peak and power measurement of N fuel element rupture detection,
Characterized in that, the bypass circulation is provided with valve, opening valve at steady peak or measurement reactor capability forms and is responsible for
The connection in road.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710964579.7A CN107644695B (en) | 2017-10-17 | 2017-10-17 | One kind is based on16The method at the steady peak and power measurement of the fuel element rupture detection of N |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710964579.7A CN107644695B (en) | 2017-10-17 | 2017-10-17 | One kind is based on16The method at the steady peak and power measurement of the fuel element rupture detection of N |
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| CN107644695A true CN107644695A (en) | 2018-01-30 |
| CN107644695B CN107644695B (en) | 2019-05-21 |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN109495987A (en) * | 2018-10-24 | 2019-03-19 | 四川同人精工科技有限公司 | A kind of electrical heating elements deformation detection control system |
| CN110033873A (en) * | 2019-04-25 | 2019-07-19 | 广西防城港核电有限公司 | Method for analyzing and judging nuclear fuel assembly breakage |
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| JP2012007889A (en) * | 2010-06-22 | 2012-01-12 | Hitachi-Ge Nuclear Energy Ltd | Radiation monitor and method for gain compensation of the same |
| CN103985423A (en) * | 2014-05-21 | 2014-08-13 | 田志恒 | Method for monitoring 16N leaking from nuclear power reactor vapor generator |
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2017
- 2017-10-17 CN CN201710964579.7A patent/CN107644695B/en active Active
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
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| JP2012007889A (en) * | 2010-06-22 | 2012-01-12 | Hitachi-Ge Nuclear Energy Ltd | Radiation monitor and method for gain compensation of the same |
| CN103985423A (en) * | 2014-05-21 | 2014-08-13 | 田志恒 | Method for monitoring 16N leaking from nuclear power reactor vapor generator |
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| 尤伟等: "压水堆核电机组一回路裂变产物源项分析", 《中国科技成果》 * |
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| 郑军伟等: "核电厂主蒸汽16N监测用于蒸汽发生器泄漏率测量的研究", 《中国核电》 * |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109495987A (en) * | 2018-10-24 | 2019-03-19 | 四川同人精工科技有限公司 | A kind of electrical heating elements deformation detection control system |
| CN110033873A (en) * | 2019-04-25 | 2019-07-19 | 广西防城港核电有限公司 | Method for analyzing and judging nuclear fuel assembly breakage |
| CN110033873B (en) * | 2019-04-25 | 2021-11-26 | 广西防城港核电有限公司 | Method for analyzing and judging breakage of nuclear fuel assembly |
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| Publication number | Publication date |
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| CN107644695B (en) | 2019-05-21 |
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