CN110749919A - Method and device for calibrating nuclear reactor out-of-pile detector - Google Patents
Method and device for calibrating nuclear reactor out-of-pile detector Download PDFInfo
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- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/16—Measuring radiation intensity
- G01T1/185—Measuring radiation intensity with ionisation chamber arrangements
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- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
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- G01T7/005—Details of radiation-measuring instruments calibration techniques
Abstract
The invention discloses a method and a device for calibrating a nuclear reactor out-of-pile detector, wherein the method comprises the following steps: constructing a linear relation between the in-core axial deviation and the out-core axial deviation and the core power measurement: the off-stack measured off-stack axial offset is equal to the first linear fit coefficient plus the product of the in-stack measured in-stack axial offset and the second linear fit coefficient; the sum of the equivalent currents of the upper section and the lower section is equal to the product of the third linear fitting coefficient and the power measured by the out-of-pile two-loop heat balance test; obtaining a constant value of the second linear fitting coefficient, and calculating a first linear fitting coefficient and a third linear fitting coefficient according to the linear relation; and calculating according to the first linear fitting coefficient, the second linear fitting coefficient and the third linear fitting coefficient to obtain a first calibration coefficient, a second calibration coefficient and a third calibration coefficient for calculating the power level and the axial power deviation of the reactor. The invention can reduce artificial power disturbance of the unit, ensure the safe operation of the unit and greatly improve the economy.
Description
Technical Field
The invention relates to the technical field of nuclear instruments in nuclear reactors, in particular to a method and a device for calibrating a detector outside a nuclear reactor.
Background
A pressurized water reactor nuclear power plant is typically calibrated for an out-of-core nuclear instrumentation system located outside the reactor pressure vessel using relatively accurate measurements from the in-core instrumentation system.
In the current basic method for monitoring the reactor core of the mainstream second-generation and nuclear power station, when the in-reactor and out-of-reactor detectors are calibrated, different power distributions in the reactor need to be measured, and the corresponding relation between the in-reactor detectors and the out-of-reactor detectors is simultaneously established under different reactor core states. Specifically, calibration of the in-stack and out-of-stack detectors is required about every quarter. Usually, a multi-flux-map measurement technique is adopted, that is, axial power distribution oscillation (for example, xenon oscillation is introduced by changing the rod position of a control rod group) is artificially introduced, continuous and multiple reactor core measurements are carried out at different moments of axial power distribution change, and multiple groups of flux-map measurement data are formed by combining the measurement data of the out-of-stack detectors at the measurement moments, so that the interrelation of the in-stack detectors and the out-of-stack detectors is established.
The specific form of the calibration coefficients, which varies according to the subsequent application, generally includes the following two categories:
the correspondence between the in-stack power level and the in-stack axial power offset and the out-of-stack detector current level and the out-of-stack detector axial current offset is, for example, α (K), KU(k)，KL(k) And (3) corresponding relation calibration coefficients of the power level Pref and the axial power offset (delta phi) measured by the off-stack detector and the in-stack measurement Pref and delta phi are represented. Since Pref and Δ Φ are the main parameters for core operating interval control, these parameters are transmitted to the core control and protection system.
The in-stack axial power distribution (e.g., N segments) corresponds to the out-of-stack probe axial current reading (M segments) distribution. For example, a T matrix and an S matrix in a LOCA margin monitoring system (LSS) are corresponding relations between an in-stack axial power distribution M section and an out-stack detector current M section. The T matrix is an M multiplied by M tri-diagonal matrix and represents neutron transmission process coefficients from inside to outside of the reactor. The matrix S is an M multiplied by M single diagonal matrix and represents the sensitivity characteristic of the detector. The T matrix and the S matrix are important parameters for the LSS system to correctly monitor the LOCA allowance of the reactor core, and need to be updated regularly.
In-heap-out-of-heap flux map measurements spaced one quarter apart, about 6-8 flux maps were constructed for α (K), K, based on different times of axial power oscillationU(k)，KL(k) And updating and calculating parameters, the T matrix and the S matrix. However, this approach requires the deliberate introduction of axial power oscillations (e.g., xenon oscillations, etc.), which takes a significant amount of time to operate at low power steps. For example, in the process of starting the reactor, it takes about 16 hours to collect 3 flux map data, the reactor core needs about 24 hours to reach a steady state again, if the calibration coefficient of the out-of-reactor detector is specified to be capable of increasing power only after being corrected and input to a related system correctly, the time of low-power operation reaches several days, the economy of the power plant is seriously influenced, and the stable operation of the power plant is influenced; in addition, the sensitivity of the in-core movable probe is reduced due to frequent in-core flux map measurement, the probability of mechanical faults such as probe jamming is greatly increased, and the maintenance of the reactor core measurement system is expensive; and a simple single-flux graph measurement and superposition theoretical simulation mode is adopted, the model precision of theoretical prediction is poor, and extra errors can be introduced into calibration coefficients of in-pile and out-pile detectors.
Disclosure of Invention
The technical problem to be solved by the invention is to provide a method and a device for calibrating a nuclear reactor out-of-core detector, so as to reduce the times of calibrating inside and outside of a reactor by artificially introducing a reactor core disturbance mode, improve the economy of a nuclear power station and reduce the loss of a hardware measurement system.
In order to solve the technical problem, the invention provides a method for calibrating a nuclear reactor out-of-pile detector, which is characterized in that six separated non-compensation ionization chambers are arranged in each nuclear power range channel, each ionization chamber generates a current signal, and the six ionization chambers are equivalent to an upper section and a lower section, and the method comprises the following steps:
step S1, constructing a linear relation between the in-core axial deviation and the out-core axial deviation and the core power measurement: the off-stack measured off-stack axial offset is equal to the first linear fit coefficient plus the product of the in-stack measured in-stack axial offset and the second linear fit coefficient; the sum of the equivalent currents of the upper section and the lower section is equal to the product of the third linear fitting coefficient and the power measured by the out-of-pile two-loop heat balance test;
step S2, acquiring a constant value of the second linear fitting coefficient, and calculating a first linear fitting coefficient and a third linear fitting coefficient according to the linear relation;
and step S3, calculating and obtaining a first calibration coefficient, a second calibration coefficient and a third calibration coefficient for calculating the reactor power level and the axial power deviation according to the first linear fitting coefficient, the second linear fitting coefficient and the third linear fitting coefficient.
Preferably, the linear relation constructed in step S1 is specifically:
AOex＝a+b×AOin
IU+IL＝k·Pth
wherein, AOexAxial offset, AO, for off-stack measurementinA is a first linear fitting coefficient and b is a second linear fitting coefficient for the in-stack measured axial offset; i isU、ILThe equivalent currents of the upper section and the lower section are respectively, Pth is the power level measured by a heat balance test of the two loops outside the reactor, and k is a third linear fitting coefficient.
Preferably, the manner of obtaining the constant value of the second linear fitting coefficient in step S2 includes:
averaging a plurality of second linear fitting coefficients that have been obtained by multi-pass map measurement, the average being a constant value of the second linear fitting coefficients; or
And carrying out one-time multi-flux graph measurement, and taking the value of the obtained second linear fitting coefficient as a constant value of the second linear fitting coefficient.
Preferably, the manner of calculating the first calibration coefficient, the second calibration coefficient, and the third calibration coefficient in step S3 is specifically as follows:
α＝[1－(a/100)2]/b
KU＝1/[k(1+a/100)]
KL＝1/[k(1－a/100)]
wherein α is the first calibration factor, KUFor the second calibration factor, KLIs the third calibration factor.
The invention also provides a device for calibrating the detector outside the nuclear reactor, wherein six separated non-compensation ionization chambers are arranged in each nuclear power range channel, each ionization chamber generates a current signal, and the six ionization chambers are equivalent to an upper section and a lower section, and the device comprises:
the construction unit is used for constructing a linear relation between the in-core axial deviation and the out-core axial deviation and the core power measurement: the off-stack measured off-stack axial offset is equal to the first linear fit coefficient plus the product of the in-stack measured in-stack axial offset and the second linear fit coefficient; the sum of the equivalent currents of the upper section and the lower section is equal to the product of the third linear fitting coefficient and the power measured by the out-of-pile two-loop heat balance test;
the first calculation unit is used for acquiring a constant value of the second linear fitting coefficient and calculating a first linear fitting coefficient and a third linear fitting coefficient according to the linear relation;
and the second calculation unit is used for calculating and obtaining a first calibration coefficient, a second calibration coefficient and a third calibration coefficient for calculating the power level and the axial power deviation of the reactor according to the first linear fitting coefficient, the second linear fitting coefficient and the third linear fitting coefficient.
Preferably, the linear relation constructed by the construction unit is specifically as follows:
AOex＝a+b×AOin
IU+IL＝k·Pth
wherein, AOexAxial offset, AO, for off-stack measurementinA is a first linear fitting coefficient and b is a second linear fitting coefficient for the in-stack measured axial offset; i isU、ILRespectively, the upper and lower section equivalent currents, Pth is the outside of the stackThe power level measured by the two-loop thermal equilibrium test, k, is the third linear fit coefficient.
Preferably, the manner in which the first calculation unit obtains the constant value of the second linear fitting coefficient includes:
averaging a plurality of second linear fitting coefficients that have been obtained by multi-pass map measurement, the average being a constant value of the second linear fitting coefficients; or
And carrying out one-time multi-flux graph measurement, and taking the value of the obtained second linear fitting coefficient as a constant value of the second linear fitting coefficient.
Preferably, the way of calculating the first calibration coefficient, the second calibration coefficient, and the third calibration coefficient by the second calculating unit is specifically:
α＝[1－(a/100)2]/b
KU＝1/[k(1+a/100)]
KL＝1/[k(1－a/100)]
wherein α is the first calibration factor, KUFor the second calibration factor, KLIs the third calibration factor.
The embodiment of the invention has the following beneficial effects:
the invention can greatly reduce the times of using reactor core hardware for measurement, reduce the loss of a measurement hardware system and greatly improve the economy;
the invention can optimize the current reactor core operation environment, avoid the introduction of artificial axial power distribution oscillation, and greatly improve the safety and the economy of the power plant operation;
the invention adopts a simplified calculation form to replace the actual disturbance of the reactor core, reduces the influence of misoperation of an operator, and can also reduce the workload of unit operation support personnel;
the method can effectively shorten the time of the reactor power-per-liter physical experiment and improve the economy.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only some embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to the drawings without creative efforts.
Fig. 1 is a schematic flow chart illustrating a method for calibrating an out-of-core detector of a nuclear reactor according to an embodiment of the present invention.
FIG. 2 is a schematic diagram of the position of an off-stack detector in an embodiment of the invention.
FIG. 3 is a schematic diagram of a power span channel geometry in an embodiment of the present invention.
Detailed Description
The following description of the embodiments refers to the accompanying drawings, which are included to illustrate specific embodiments in which the invention may be practiced.
Referring to fig. 1, an embodiment of the present invention provides a method for calibrating a nuclear reactor out-of-core detector, where six separate uncompensated ionization chambers are arranged in each nuclear power range channel, each ionization chamber generates a current signal, and the six ionization chambers are equivalent to an upper section and a lower section, the method includes:
step S1, constructing a linear relation between the in-core axial deviation and the out-core axial deviation and the core power measurement: the off-stack measured off-stack axial offset is equal to the first linear fit coefficient plus the product of the in-stack measured in-stack axial offset and the second linear fit coefficient; the sum of the equivalent currents of the upper section and the lower section is equal to the product of the third linear fitting coefficient and the power measured by the out-of-pile two-loop heat balance test;
step S2, acquiring a constant value of the second linear fitting coefficient, and calculating a first linear fitting coefficient and a third linear fitting coefficient according to the linear relation;
and step S3, calculating and obtaining a first calibration coefficient, a second calibration coefficient and a third calibration coefficient for calculating the reactor power level and the axial power deviation according to the first linear fitting coefficient, the second linear fitting coefficient and the third linear fitting coefficient.
Specifically, for a pressurized water reactor nuclear power plant, as shown in FIG. 2, there are four nuclear power range channels for the out-of-core nuclear instrumentation system located outside of the reactor pressure vessel. As shown in FIG. 3, six separate uncompensated ionization chambers are arranged in each nuclear power range channel, each ionization chamber is 607mm long, and a neutron sensitive section is 100mm long. Each section of the ionization chamber generates a current signal Ii (i ═ 1, 6). The six sections of ionization chambers are equivalent to an upper section and a lower section, and then an equivalent current signal of the upper section is defined as:
the lower equivalent current signal is defined as:
for the power span channel k (k ═ 1,4), the reactor power level PR and the axial power deviation Δ Φ are calculated as follows:
PR(k)＝KU(k)×IU(k)+KL(k)×IL(k)
ΔΦ(k)＝α(k)[KU(k)×IU(k)－KL(k)×IL(k)]
ΔΦ＝AO×PR
wherein, IUAnd ILAre equivalent current signals of the upper and lower segments, α and KUAnd KLAre all calibration coefficients, PR and Δ Φ are in% FP, KUAnd KLIs% FP/. mu.A, α is dimensionless, AO is the axial power offset.
Since the same physical quantity AO and the core power are measured by the in-core measurement system and the out-core instrumentation system, the linear relation between the in-core and out-core axial offset AO and the core power measurement is constructed in step S1 as follows:
AOex＝a+b×AOin(1)
IU+IL＝k·Pth (2)
in equation (1): AOexAxial offset, AO, for off-stack measurementinFor axial offset measured in the stack, a isOne linear fitting coefficient, b is the second linear fitting coefficient. In equation (2): i isU、ILThe equivalent currents of the upper section and the lower section are measured by an out-of-reactor nuclear instrument system, the sum of the equivalent currents of the upper section and the lower section represents the total power of a reactor core, Pth is the power level measured by an out-of-reactor two-loop heat balance test, and k is a third linear fitting coefficient.
As described in the background section, by artificially introducing axial power distribution oscillation (for example, changing the rod position of a control rod group to introduce xenon oscillation) and carrying out continuous multiple reactor core measurements at different moments of axial power distribution change, a plurality of groups of in-reactor flux map measurement data with different AO are formed, the in-reactor and out-of-reactor detector measurement data at the measurement moments are combined to establish the inter-reactor and out-of-reactor detector correlation, and then the linear fitting method is adopted to determine α, KU and KL dimensionless coefficients.
The inventor of the invention finds that on the basis of the analysis of a large amount of previous measurement data and in combination with the analysis of the physical significance of the measurement data: as can be seen from equations (1), (2): if a parameter is fixed, e.g. the second linear fit coefficient "b" is constant, then an out-of-pile, in-pile measurement (AO) is takenex、AOin、IU、ILPth) can determine the remaining two coefficients, i.e. the first linear fitting coefficient a and the third linear fitting coefficient k, without performing multi-pass graph measurement as in the prior art, and then three linear fitting coefficients k, a and b are obtained by a least square fitting method.
It should be noted that it is realistic that the step S2 takes the second linear fitting coefficient "b" as a constant: for the nuclear power station which adopts the measurement of the excessive flux map, the value of a second linear fitting coefficient 'b' can be determined according to a large number of k, a and b coefficients which have already finished the test, and the specific mode can be the average value of b in the measurement of a plurality of times; for a nuclear power plant which does not perform multi-flux map measurement, one multi-flux map measurement can be performed to determine a group of k, a and b coefficients, and the value of a second linear fitting coefficient 'b' is determined from the k, a and b coefficients.
The method in which the second linear fitting coefficient "b" is constant also has an interpretable physical meaning: the reactor core structure, the out-of-reactor arrangement and the size of the reactor of the nuclear power plant are fixed after the reactor is built, the arrangement position of the in-reactor fuel assemblies is also fixed, the relative power distribution of the in-reactor fuel assemblies tends to be consistent under the condition that the fuel management modes converge, in addition, the performance of an out-of-reactor nuclear instrument system is more stable, and the change is not large in the whole service life. Therefore, the process that neutrons are transmitted from the inside to the outside of the reactor and are detected by the outside nuclear instrument system also has the trend, and the change process of the inside nuclear measurement system and the outside nuclear instrument system has the characteristic of stability in the service life of the power station when the same physical quantity AO and the core power are measured, so that the slope coefficient 'b' (in the formula (1), b is located at the slope position) between the inside nuclear measurement system and the outside nuclear instrument system can be fixed and is constant.
After acquiring K, a, b at step S2, step S3 determines the first calibration coefficient α and the second calibration coefficient K, respectively, according to the following mannerUThe third calibration coefficient KL：
α＝[1－(a/100)2]/b
KU＝1/[k(1+a/100)]
KL＝1/[k(1－a/100)]
Reconstruction of the movable probe measurements provided by the flux map processing program to provide the core axial offset AOinThe power level Pth (dimension% FP) measured by the out-of-core two-loop heat balance test gives the actual power level during the measurement, whereby the core axial power deviation is as follows:
ΔΦin＝AOin×Pth/100
for each power range channel k, the error δ 1(k) of the high nuclear flux scram set point and the error δ 2(k) of the axial power deviation can be calculated:
δ1(k)＝Pth－PR(k)
δ2(k)＝ΔΦin－ΔΦ(k)
by comparing the calibration coefficients α, KU、KLTo meet the requirements ofAcceptance criterion | δ1(k)|<5% sum | δ2(k)|<3％。
From the analysis of a large amount of measurement data of the nuclear power plant, the effect of the embodiment can also be proved:
TABLE 1 cycle 1 of No. 1 nuclear power plant
TABLE 2 cycle 3 of No. 1 plant of certain nuclear power plant
TABLE 3 cycle 5 of No. 1 plant of certain nuclear power plant
TABLE 4 number 3 cycle of No. 2 nuclear power plant
As can be seen from data of "cycle 1 of machine No. 1 of a certain nuclear power plant" in table 1, on two power steps of 50% and 75%, coefficients "b" obtained after measurement processing of four power range channels by adopting a multi-flux diagram are basically the same; as can be seen from the data of "cycle 3 of machine No. 1 in certain nuclear power plant" in table 2 and "cycle 5 of machine No. 1 in certain nuclear power plant" in table 3, the coefficients "b" obtained after the four power range channels are measured and processed by adopting a multi-flux map are basically the same along with the fuel consumption and different cycles in a certain cycle; as can be seen from data of cycle 3 of a machine No. 2 in a certain nuclear power plant in the table 4 and data in tables 1 to 3, coefficients of 'b' obtained after four power range channels are measured and processed by adopting a multi-flux diagram are basically the same among different machine sets.
As can be seen from the above description of the embodiments, the embodiments of the present invention have the following beneficial effects:
the invention can greatly reduce the times of using reactor core hardware for measurement, reduce the loss of a measurement hardware system and greatly improve the economy;
the invention can optimize the current reactor core operation environment, avoid the introduction of artificial axial power distribution oscillation, and greatly improve the safety and the economy of the power plant operation;
the invention adopts a simplified calculation form to replace the actual disturbance of the reactor core, reduces the influence of misoperation of an operator, and can also reduce the workload of unit operation support personnel;
the method can effectively shorten the time of the reactor power-per-liter physical experiment and improve the economy.
The above disclosure is only for the purpose of illustrating the preferred embodiments of the present invention, and it is therefore to be understood that the invention is not limited by the scope of the appended claims.
Claims (8)
1. A method for calibrating a nuclear reactor out-of-core detector, wherein six separate uncompensated ionization chambers are arranged in each nuclear power range channel, each ionization chamber generates a current signal, and the six ionization chambers are equivalently divided into an upper section and a lower section, the method comprises the following steps:
step S1, constructing a linear relation between the in-core axial deviation and the out-core axial deviation and the core power measurement: the off-stack measured off-stack axial offset is equal to the first linear fit coefficient plus the product of the in-stack measured in-stack axial offset and the second linear fit coefficient; the sum of the equivalent currents of the upper section and the lower section is equal to the product of the third linear fitting coefficient and the power measured by the out-of-pile two-loop heat balance test;
step S2, acquiring a constant value of the second linear fitting coefficient, and calculating a first linear fitting coefficient and a third linear fitting coefficient according to the linear relation;
and step S3, calculating and obtaining a first calibration coefficient, a second calibration coefficient and a third calibration coefficient for calculating the reactor power level and the axial power deviation according to the first linear fitting coefficient, the second linear fitting coefficient and the third linear fitting coefficient.
2. The method according to claim 1, wherein the linear relation constructed in step S1 is specifically:
AOex＝a+b×AOin
IU+IL＝k·Pth
wherein, AOexAxial offset, AO, for off-stack measurementinA is a first linear fitting coefficient and b is a second linear fitting coefficient for the in-stack measured axial offset; i isU、ILThe equivalent currents of the upper section and the lower section are respectively, Pth is the power level measured by a heat balance test of the two loops outside the reactor, and k is a third linear fitting coefficient.
3. The method according to claim 2, wherein the manner of obtaining the constant value of the second linear fitting coefficient in step S2 includes:
averaging a plurality of second linear fitting coefficients that have been obtained by multi-pass map measurement, the average being a constant value of the second linear fitting coefficients; or
And carrying out one-time multi-flux graph measurement, and taking the value of the obtained second linear fitting coefficient as a constant value of the second linear fitting coefficient.
4. The method according to claim 2, wherein the first calibration coefficient, the second calibration coefficient, and the third calibration coefficient are calculated in step S3 specifically by:
α＝[1－(a/100)2]/b
KU＝1/[k(1+a/100)]
KL＝1/[k(1－a/100)]
wherein α is the first calibration factor, KUFor the second calibration factor, KLIs the third calibration factor.
5. An apparatus for calibrating a nuclear reactor detector outside the reactor, wherein six separate uncompensated ionization chambers are arranged in each nuclear power range channel, each ionization chamber generates a current signal, and the six ionization chambers are equivalently divided into an upper section and a lower section, the apparatus comprising:
the construction unit is used for constructing a linear relation between the in-core axial deviation and the out-core axial deviation and the core power measurement: the off-stack measured off-stack axial offset is equal to the first linear fit coefficient plus the product of the in-stack measured in-stack axial offset and the second linear fit coefficient; the sum of the equivalent currents of the upper section and the lower section is equal to the product of the third linear fitting coefficient and the power measured by the out-of-pile two-loop heat balance test;
the first calculation unit is used for acquiring a constant value of the second linear fitting coefficient and calculating a first linear fitting coefficient and a third linear fitting coefficient according to the linear relation;
and the second calculation unit is used for calculating and obtaining a first calibration coefficient, a second calibration coefficient and a third calibration coefficient for calculating the power level and the axial power deviation of the reactor according to the first linear fitting coefficient, the second linear fitting coefficient and the third linear fitting coefficient.
6. The apparatus according to claim 5, wherein the linear relation constructed by the construction unit is specifically:
AOex＝a+b×AOin
IU+IL＝k·Pth
wherein, AOexAxial offset, AO, for off-stack measurementinA is a first linear fitting coefficient and b is a second linear fitting coefficient for the in-stack measured axial offset; i isU、ILThe equivalent currents of the upper section and the lower section are respectively, Pth is the power level measured by a heat balance test of the two loops outside the reactor, and k is a third linear fitting coefficient.
7. The apparatus according to claim 6, wherein the manner in which the first calculation unit obtains the constant value of the second linear fitting coefficient includes:
averaging a plurality of second linear fitting coefficients that have been obtained by multi-pass map measurement, the average being a constant value of the second linear fitting coefficients; or
And carrying out one-time multi-flux graph measurement, and taking the value of the obtained second linear fitting coefficient as a constant value of the second linear fitting coefficient.
8. The apparatus according to claim 2, wherein the second calculating unit calculates the first calibration coefficient, the second calibration coefficient, and the third calibration coefficient by:
α＝[1－(a/100)2]/b
KU＝1/[k(1+a/100)]
KL＝1/[k(1－a/100)]
wherein α is the first calibration factor, KUFor the second calibration factor, KLIs the third calibration factor.
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| CN108172312A (en) * | 2017-12-13 | 2018-06-15 | 广东核电合营有限公司 | The calibration method of the Axial power difference of nuclear power station out-pile Nuclear Instrument system |
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| CN113270217A (en) * | 2021-05-14 | 2021-08-17 | 中国核动力研究设计院 | Power range measuring method and device of six-section uncompensated ionization chamber |
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