CN107863164B - A kind of method of nuclear power plant's out-pile nuclear measurement system design factor calibration - Google Patents
A kind of method of nuclear power plant's out-pile nuclear measurement system design factor calibration Download PDFInfo
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- CN107863164B CN107863164B CN201711021595.9A CN201711021595A CN107863164B CN 107863164 B CN107863164 B CN 107863164B CN 201711021595 A CN201711021595 A CN 201711021595A CN 107863164 B CN107863164 B CN 107863164B
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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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- 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
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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
Abstract
The invention belongs to nuclear power plant's reactor cores to supervise technical field, and in particular to a kind of method of nuclear power plant's out-pile nuclear measurement system design factor calibration.Derived by theoretical calculation, out-pile Nuclear Instrument system-computed derives, theoretical correction method calculate derive, the realization of nuclear power plant's theoretical correction method and etc. realize this method.Overhaul main line time (3 hour/time) has been saved by the use of this method, has reduced 25.8 tons/single fighter/single cycle Spent Radioactive liquid measure, reduces unit operation operation risk, while having extended measuring system in heap and popping one's head in the service life.
Description
Technical field
The invention belongs to nuclear power plant's reactor cores to supervise technical field, and in particular to a kind of nuclear power plant's out-pile nuclear measurement system calculating
The method of coefficient calibration.
Background technique
At present nuclear power plant using the mobile test method for changing axial power excursion in reactor core of xenon oscillation or control rod come into
The scale test of row nuclear power plant out-pile Nuclear measurement system design factor.It is quasi- that out-pile Nuclear measurement system after scale need to meet following examination
Then:
|PKME- Pr (k) | < 5%FP, i.e. power deviation Δ Pr < 5%FP.
|ΔIinΔ I (k) | < 3%FP, i.e. difference Δ (Δ I) < 3%FP of Axial power difference.
Easily cause heap in-core xenon oscillation using existing method, is unfavorable for operator and carries out reactor core control；The test occupies big
Measure the overhaul main line time；About 25.8 tons/single fighter/single cycle Spent Radioactive liquid measure can be generated.
Therefore, a kind of method researched and developed, design nuclear power plant's out-pile nuclear measurement system design factor calibration, to solve above-mentioned skill
Art problem.
Summary of the invention
The technical problem to be solved in the present invention is to provide a kind of sides of nuclear power plant's out-pile nuclear measurement system design factor calibration
Method efficiently and accurately carries out the calibration of out-pile nuclear measurement system design factor using this method.
In order to realize the purpose, the technical solution adopted by the present invention is that:
A kind of method of nuclear power plant's out-pile nuclear measurement system design factor calibration, by following step to out-pile Nuclear measurement system
Design factor carries out school quarter:
(a) theoretical calculation derives
When the axial power in reactor deviates range of the AO in default, axial power in reactor is determined
Deviate AOinWith power excursion AO axial outside reactorexThere are linear relationships, and out-pile neutron flux and core power are at just
Than physical relationship such as formula (1) and formula (2)；
φH+φB=W × K (2)
Wherein, φH、φBFor out-pile upper and lower part neutron flux；
AOexFor power excursion axial outside reactor；
AOinFor power excursion axial in reactor；
A, B is linear coefficient, related to reactor burnup；
W is heat output of reactor；
K is power-neutron flux conversion coefficient；
There are following relationships: Δ I=AO with power excursion axial in reactor by Axial power difference Δ Iin× W then will
(1), (2) are brought the formula into and are obtained:
Further abbreviation obtains:
Above formula is the relationship of Axial power difference Δ I Yu out-pile upper and lower part neutron flux；
Out-pile neutron-flux level can not directly measure to obtain, and be characterized using the current value of ex-core detector measurement；
The electric current of ex-core detector measurement is directly proportional to neutron flux, there is following relationship:
φH=a × IH、φB=b × IB
In formula, IH、IBThe current value obtained for out-pile upper and lower part detector measurement；
A, b is flux-electric current conversion coefficient of out-pile upper and lower part detector, is had with the detection efficient of ex-core detector
It closes；
Bringing the relational expression into (3) can obtain:
Above formula is the relationship of Axial power difference Δ I Yu out-pile upper and lower part detector measurement electric current；
(b) out-pile Nuclear Instrument system-computed derives
Electric current that PWR nuclear power plant out-pile Nuclear Instrument system power range ionisation chamber detects and with reactor capability at
Direct ratio, relational expression are as follows:
IH+IB=K' × W (5)
In formula: K' is power-electric current conversion coefficient；
The I obtained according to measurementH、IBAnd the heat output of reactor W obtained according to nuclear power plant's secondary circuit instrument measurement, it asks
K' value out；
Axial power excursion AO in the reactor of actual measurementinWith power excursion AO axial outside reactorexMeet following
Relational expression:
AOex=A'+B' × AOin (6)
A ', B ' are axial power excursion AO in the reactor of actual measurementinWith power excursion AO axial outside reactorex
Linear relationship in linear coefficient；
It enables:
It is obtained by (7) formula:
It can be obtained from (5) formula:
(8), (9) formula substitutes into (6) formula and obtains:
The measured value calculation formula of the Δ I ' of out-pile Nuclear Instrument system actual measurement is as follows:
That is:
(c) theoretical correction method, which calculates, derives
It vibrates to obtain Δ I, I by nuclear design software Simulation Core axial powerH、IB, A, B calculated value；
The Δ I of theoretical calculation is identical as the Δ I ' of out-pile Nuclear Instrument system actual measurement, obtains in conjunction with formula (4), (10):
Simultaneous (11)-(13) formula obtains:
From (14), (15) formula: the detection efficient of the outer top and the bottom detector of A, B and reactor core of A', B' and theoretical calculation
Relative value it is related, when the detection efficient of the outside upper lower current of reactor core is consistent, A', B' are equal with A, B；
After acquiring A', B', in conjunction with K', formula (10) are brought into, obtain out-pile nuclear measurement system power range and calculate the factor:
(d) realization of nuclear power plant's theoretical correction method
According to formula (14)-(18) derivation: to obtain out-pile nuclear measurement system power range design factor α,
KH、KB, need to know the relative ratio of A, B, K' and a, b；
Theoretic A, B is calculated in nuclear design software by having reactor periphery neutron flux computing function；
A, the ratio of b passes through φ in theoretical calculationH、φBThe I obtained with actual measurementH、IBRatio acquire；
The I that K' passes through actual measurementH、IB, W acquires according to (5) formula.
The beneficial effect of technical solution of the present invention is: technical solution of the present invention will not cause xenon oscillation, can save big
It repairs the main line time, reduces Spent Radioactive liquid measure, reduce unit operation operation risk, while extending the survey of compacted clay liners reactor core
The probe service life of amount system (hereinafter referred to as).
Specific embodiment
Technical solution of the present invention is described in detail combined with specific embodiments below.
A kind of method of nuclear power plant's out-pile nuclear measurement system design factor calibration of the present invention, by following step to heap outer core
Examining system design factor carries out school quarter:
(a) theoretical calculation derives
When the axial power in reactor deviates range of the AO in default, axial power in reactor is determined
Deviate AOinWith power excursion AO axial outside reactorexThere are linear relationships, and out-pile neutron flux and core power are at just
Than physical relationship such as formula (1) and formula (2)；
φH+φB=W × K (2)
Wherein, φH、φBFor out-pile upper and lower part neutron flux；
AOexFor power excursion axial outside reactor；
AOinFor power excursion axial in reactor；
A, B is linear coefficient, related to reactor burnup；
W is heat output of reactor；
K is power-neutron flux conversion coefficient；
There are following relationships: Δ I=AO with power excursion axial in reactor by Axial power difference Δ Iin× W then will
(1), (2) are brought the formula into and are obtained:
Further abbreviation obtains:
Above formula is the relationship of Axial power difference Δ I Yu out-pile upper and lower part neutron flux；
Out-pile neutron-flux level can not directly measure to obtain, and be characterized using the current value of ex-core detector measurement；
The electric current of ex-core detector measurement is directly proportional to neutron flux, there is following relationship:
φH=a × IH、φB=b × IB
In formula, IH、IBThe current value obtained for out-pile upper and lower part detector measurement；
A, b is flux-electric current conversion coefficient of out-pile upper and lower part detector, is had with the detection efficient of ex-core detector
It closes；
Bringing the relational expression into (3) can obtain:
Above formula is the relationship of Axial power difference Δ I Yu out-pile upper and lower part detector measurement electric current；
(b) out-pile Nuclear Instrument system-computed derives
Electric current that PWR nuclear power plant out-pile Nuclear Instrument system power range ionisation chamber detects and with reactor capability at
Direct ratio, relational expression are as follows:
IH+IB=K' × W (5)
In formula: K' is power-electric current conversion coefficient；
The I obtained according to measurementH、IBAnd the heat output of reactor W obtained according to nuclear power plant's secondary circuit instrument measurement, it asks
K' value out；
Axial power excursion AO in the reactor of actual measurementinWith power excursion AO axial outside reactorexMeet following
Relational expression:
AOex=A'+B' × AOin (6)
A ', B ' are axial power excursion AO in the reactor of actual measurementinWith power excursion AO axial outside reactorex
Linear relationship in linear coefficient；
It enables:
It is obtained by (7) formula:
It can be obtained from (5) formula:
(8), (9) formula substitutes into (6) formula and obtains:
The measured value calculation formula of the Δ I ' of out-pile Nuclear Instrument system actual measurement is as follows:
That is:
(c) theoretical correction method, which calculates, derives
It vibrates to obtain Δ I, I by nuclear design software Simulation Core axial powerH、IB, A, B calculated value；
The Δ I of theoretical calculation is identical as the Δ I ' of out-pile Nuclear Instrument system actual measurement, obtains in conjunction with formula (4), (10):
Simultaneous (11)-(13) formula obtains:
From (14), (15) formula: the detection efficient of the outer top and the bottom detector of A, B and reactor core of A', B' and theoretical calculation
Relative value it is related, when the detection efficient of the outside upper lower current of reactor core is consistent, A', B' are equal with A, B；
After acquiring A', B', in conjunction with K', formula (10) are brought into, obtain out-pile nuclear measurement system power range and calculate the factor:
(d) realization of nuclear power plant's theoretical correction method
According to formula (14)-(18) derivation: to obtain out-pile nuclear measurement system power range design factor α,
KH、KB, need to know the relative ratio of A, B, K' and a, b；
Theoretic A, B is calculated in nuclear design software by having reactor periphery neutron flux computing function；
A, the ratio of b passes through φ in theoretical calculationH、φBThe I obtained with actual measurementH、IBRatio acquire；
The I that K' passes through actual measurementH、IB, W acquires according to (5) formula.
The verifying of out-pile nuclear measurement system power range scale test data is recycled by Fuqing nuclear power plant U1C2, U2C1,
The core power and Axial power difference being calculated using Fuqing nuclear power plant theoretical correction method are all satisfied test acceptance criteria, error
Suitable with existing method, this method can theoretically substitute traditional test method.
Overhaul main line time (3 hour/time) has been saved by the use of this method, has reduced 25.8 tons/single fighter/Dan Xun
Ring Spent Radioactive liquid measure, reduces unit operation operation risk, while extending measuring system in heap and popping one's head in the service life.
Claims (1)
1. a kind of method of nuclear power plant's out-pile nuclear measurement system design factor calibration, which is characterized in that by following step to heap
Outer Nuclear measurement system design factor carries out school quarter:
(a) theoretical calculation derives
When the axial power in reactor deviates range of the AO in default, axial power excursion in reactor is determined
AOinWith power excursion AO axial outside reactorexThere are linear relationships, and out-pile neutron flux is directly proportional to core power, tool
Body relationship such as formula (1) and formula (2)；
φH+φB=W × K (2)
Wherein, φH、φBFor out-pile upper and lower part neutron flux；
AOexFor power excursion axial outside reactor；
AOinFor power excursion axial in reactor；
A, B is linear coefficient, related to reactor burnup；
W is heat output of reactor；
K is power-neutron flux conversion coefficient；
There are following relationships: Δ I=AO with power excursion axial in reactor by Axial power difference Δ Iin× W, then by (1),
(2) formula is brought into obtain:
Further abbreviation obtains:
Above formula is the relationship of Axial power difference Δ I Yu out-pile upper and lower part neutron flux；
Out-pile neutron-flux level can not directly measure to obtain, and be characterized using the current value of ex-core detector measurement；
The electric current of ex-core detector measurement is directly proportional to neutron flux, there is following relationship:
φH=a × IH、φB=b × IB
In formula, IH、IBThe current value obtained for out-pile upper and lower part detector measurement；
A, b is flux-electric current conversion coefficient of out-pile upper and lower part detector, related with the detection efficient of ex-core detector；
Bringing the relational expression into (3) can obtain:
Above formula is the relationship of Axial power difference Δ I Yu out-pile upper and lower part detector measurement electric current；
(b) out-pile Nuclear Instrument system-computed derives
Electric current that PWR nuclear power plant out-pile Nuclear Instrument system power range ionisation chamber detects and directly proportional to reactor capability,
Its relational expression are as follows:
IH+IB=K' × W (5)
In formula: K' is power-electric current conversion coefficient；
The I obtained according to measurementH、IBAnd the heat output of reactor W obtained according to nuclear power plant's secondary circuit instrument measurement, find out K'
Value；
Axial power excursion AO in the reactor of actual measurementinWith power excursion AO axial outside reactorexMeet following relationship
Formula:
AOex=A'+B' × AOin (6)
A ', B ' are axial power excursion AO in the reactor of actual measurementinWith power excursion AO axial outside reactorexIt is linear
Linear coefficient in relationship；
It enables:
It is obtained by (7) formula:
It can be obtained from (5) formula:
(8), (9) formula substitutes into (6) formula and obtains:
The measured value calculation formula of the Δ I ' of out-pile Nuclear Instrument system actual measurement is as follows:
That is:
(c) theoretical correction method, which calculates, derives
It vibrates to obtain Δ I, I by nuclear design software Simulation Core axial powerH、IB, A, B calculated value；
The Δ I of theoretical calculation is identical as the Δ I ' of out-pile Nuclear Instrument system actual measurement, obtains in conjunction with formula (4), (10):
Simultaneous (11)-(13) formula obtains:
From (14), (15) formula: the phase of A', B' and the detection efficient of the outer top and the bottom detector of A, B and reactor core of theoretical calculation
Related to being worth, when the detection efficient of the outside upper lower current of reactor core is consistent, A', B' are equal with A, B；
After acquiring A', B', in conjunction with K', formula (10) are brought into, obtain out-pile nuclear measurement system power range and calculate the factor:
(d) realization of nuclear power plant's theoretical correction method
According to formula (14)-(18) derivation: to obtain out-pile nuclear measurement system power range design factor α, KH、KB,
Need to know the relative ratio of A, B, K' and a, b；
Theoretic A, B is calculated in nuclear design software by having reactor periphery neutron flux computing function；
A, the ratio of b passes through φ in theoretical calculationH、φBThe I obtained with actual measurementH、IBRatio acquire；
The I that K' passes through actual measurementH、IB, W acquires according to (5) formula.
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| CN109031396B (en) * | 2018-05-24 | 2020-09-18 | 岭东核电有限公司 | Nuclear instrument system parameter calibration method, device and system |
| CN109817360B (en) * | 2019-01-22 | 2022-02-08 | 广西防城港核电有限公司 | Prediction method for predicting nuclear thermal power deviation and Gk parameter trend of RPN system |
| CN110749919A (en) * | 2019-10-12 | 2020-02-04 | 中广核研究院有限公司 | Method and device for calibrating nuclear reactor out-of-pile detector |
| CN115050496B (en) * | 2022-08-11 | 2022-11-25 | 西安交通大学 | Single-point calibration method for external detector of pressurized water reactor |
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