CN113297529A - Method for pre-measuring circular shutdown date of pressurized water reactor - Google Patents

Method for pre-measuring circular shutdown date of pressurized water reactor Download PDF

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CN113297529A
CN113297529A CN202110403299.5A CN202110403299A CN113297529A CN 113297529 A CN113297529 A CN 113297529A CN 202110403299 A CN202110403299 A CN 202110403299A CN 113297529 A CN113297529 A CN 113297529A
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高永恒
詹勇杰
邓志新
刘臻
沈亚杰
杨嗣
王澄瀚
王勇智
任忠
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CNNC Nuclear Power Operation Management Co Ltd
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Abstract

The invention relates to a method for predicting the circular shutdown date of a reactor of a nuclear power station, which comprises the following steps: the measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure DDA0003021209990000011
Calculating the theoretical average boron reduction rate in the current cycle residual life
Figure DDA0003021209990000012
Calculating the current monthly average nuclear reactor power Pr(ii) a Predicting a reactor shutdown date of the nuclear power plant according to the following formula:
Figure DDA0003021209990000013
wherein T is predicted trip date, T0Is the current date, CEOLThe minimum operable boron concentration at the end of the life. The method provided by the invention is used for correcting the critical boron concentration of the current actual measurement state to the reference state
Figure DDA0003021209990000014
Adding correction to boron 10 abundance and samarium toxicity, and using theoretical average boron reduction rate in the remaining life of the current cycle
Figure DDA0003021209990000015
Replacing the current monthly average boron rate-reduction v, using historical statistical average nuclear reactor power over the corresponding time period over the remaining life
Figure DDA0003021209990000016
Substituted current monthly average nuclear reactor power PrThe prediction stability is high, and the result accuracy is relatively and greatly improved.

Description

Method for pre-measuring circular shutdown date of pressurized water reactor
Technical Field
The invention belongs to the technical field of nuclear power plant reactor core supervision, and particularly relates to a method for pre-measuring the circular shutdown date of a pressurized water reactor.
Background
The prediction of the shutdown date of the pressurized water reactor is directly related to the determination of the shutdown overhaul date, the arrangement of an overhaul plan, the preparation of fuel and the like, so that the accurate prediction of the shutdown date of the pressurized water reactor is an important work before shutdown. When predicting the shutdown date, core total burnup statistics and core reactivity change tracking must be performed. The critical state of full power, full control rod lifting and xenon balance of the reactor is taken as a reference state, when the boron concentration of the core in the reference state is reduced to 10mg/kg, the point is taken as a shutdown point, and the state of the shutdown point is taken as a state point predicted by the cycle shutdown date. In the core supervision process, the boron concentration when the reactor state obtained by actual measurement is corrected to the reference state is the corrected boron concentration, and when the corrected boron concentration is 10mg/kg, the state is the shutdown point.
The current method for predicting the circular shutdown date mainly comprises a boron drop prediction method and a fuel consumption prediction method. The fuel consumption prediction method carries out prediction on the basis of theoretical calculation data, so the precision of the fuel consumption prediction method usually depends on the precision of theoretical calculation, and the accuracy is limited. The boron drop prediction method is based on measured data for prediction. In practical application, a boron drop prediction method is mainly used, and a fuel consumption prediction method is used as an auxiliary method.
The reduction of the reactivity of the reactor is almost linearly related to the burning depth along with the deepening of the burning; for a reactor without burnable poison, along with the increase of burnup, the decrease of the critical boron concentration of a reference state is almost linearly related to the burnup depth; this is the theoretical basis for boron drop prediction. However, this linear relationship is only an approximate result and is not strictly linear, and thus the monthly boron decay rate fluctuates. The predicted shutdown date is the time for calculating the residual life of the current cycle, and the average boron reduction rate in the residual life should be theoretically used for prediction. However, in practice, we cannot obtain this value. The conventional boron drop prediction method predicts the trip date with the average boron drop rate of the past month, and the trip date thus predicted fluctuates. Especially at the beginning of the cycle life, this process fluctuation may be particularly large.
Disclosure of Invention
Therefore, the method for predicting the circular shutdown date of the pressurized water reactor is needed to solve the problem that the prediction result of the existing boron drop prediction method on the circular shutdown date of the reactor is inaccurate.
In order to achieve the above purpose, the invention provides the following technical scheme:
the invention provides a method for pre-detecting shutdown date of a pressurized water reactor, which comprises the following steps: the reactor core monitoring system monitors the actually measured boron concentration daily to obtain the actually measured boron concentration Cmes(ii) a The measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000021
Calculating the theoretical average boron reduction rate in the current cycle residual life
Figure BDA0003021209970000029
Calculating the current monthly average nuclear reactor power Pr(ii) a The pressure water reactor shutdown date is predicted according to the following formula:
Figure BDA0003021209970000022
wherein T is predicted trip date, T0Is the current date, CEOLThe minimum operable boron concentration at the end of the life.
In one embodiment, the theoretical average boron rate-of-fall over the remaining life of the current cycle is calculated
Figure BDA0003021209970000023
The method comprises the following steps: calculating the current burn-up corresponding to the theoretical critical boron concentration
Figure BDA0003021209970000024
The core monitoring system counts the current actual fuel consumption
Figure BDA0003021209970000025
Calculating theoretical fuel consumption of the reactor at the end of the cycle life
Figure BDA0003021209970000026
Calculating the theoretical average boron reduction rate in the residual service life of the current cycle according to the following formula
Figure BDA0003021209970000027
In one embodiment, the boron concentration C is measuredmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000028
The method comprises the following steps: introducing correction factors delta rho into the moderator temperature effect, control rod position effect, Doppler power effect and xenon poison effect from the measurement state to the reference state respectivelymod、ΔρRCCA、ΔρdopAnd Δ ρXeThe measured boron concentration C is determined according to the following formulamesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000031
Wherein alpha isBIs the differential value of soluble boron.
The invention also provides a method for pre-testing the shutdown date of the pressurized water reactor, which comprises the following steps: the reactor core monitoring system monitors the actually measured boron concentration daily to obtain the actually measured boron concentration Cmes(ii) a The measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000032
Calculating the average boron reduction rate v of the current month; calculating the current monthly average nuclear reactor power Pr(ii) a The pressure water reactor shutdown date is predicted according to the following formula:
Figure BDA0003021209970000033
Figure BDA0003021209970000034
wherein T is predicted trip date, T0Is the current date, CEOLThe minimum operable boron concentration at the end of the life.
In one embodiment, the method comprises the following stepsActually measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000035
The method comprises the following steps: introducing correction factors delta rho for moderator temperature effect, control rod position effect, Doppler power effect, xenon toxicity effect, boron 10 abundance and samarium toxicity effect from measurement state to reference statemod、ΔρRCCA、Δρdop、ΔρXe、ΔCBB10And Δ ρSmThe measured boron concentration C is determined according to the following formulamesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000036
Figure BDA0003021209970000037
Wherein alpha isBIs the differential value of soluble boron.
The invention also provides a method for pre-testing the shutdown date of the pressurized water reactor, which comprises the following steps: the reactor core monitoring system monitors the actually measured boron concentration daily to obtain the actually measured boron concentration Cmes(ii) a The measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000038
Calculating the average boron reduction rate v of the current month; calculating historical statistical average nuclear reactor power for respective time periods within a remaining life of a current cycle
Figure BDA0003021209970000039
The pressure water reactor shutdown date is predicted according to the following formula:
Figure BDA00030212099700000310
wherein T is predicted trip date, T0Is the current date, CEOLThe minimum operable boron concentration at the end of the life.
In one embodiment, the boron concentration C is measuredmesCorrection to referenceThe boron concentration at the time of the state is obtained as a corrected boron concentration
Figure BDA00030212099700000311
The method comprises the following steps: introducing correction factors delta rho into the moderator temperature effect, control rod position effect, Doppler power effect and xenon poison effect from the measurement state to the reference state respectivelymod、ΔρRCCA、ΔρdopAnd Δ ρXeThe measured boron concentration C is determined according to the following formulamesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000041
Wherein alpha isBIs the differential value of soluble boron.
The invention also provides a method for pre-testing the shutdown date of the pressurized water reactor, which comprises the following steps: the reactor core monitoring system monitors the actually measured boron concentration daily to obtain the actually measured boron concentration Cmes(ii) a The measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000042
Calculating the theoretical average boron reduction rate in the current cycle residual life
Figure BDA0003021209970000043
Calculating the current monthly average nuclear reactor power Pr(ii) a The pressure water reactor shutdown date is predicted according to the following formula:
Figure BDA0003021209970000044
wherein T is predicted trip date, T0Is the current date, CEOLThe minimum operable boron concentration at the end of the life.
In one embodiment, the boron concentration C is measuredmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000045
The method comprises the following steps: control rod position for moderator temperature effect from measurement state to reference stateCorrection factors delta rho introduced by effect, Doppler power effect, xenon poison effect, boron 10 abundance and samarium poison effectmod、ΔρRCCA、Δρdop、ΔρXe、ΔCBB10And Δ ρSmThe measured boron concentration C is determined according to the following formulamesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000046
Figure BDA0003021209970000047
Wherein alpha isBIs the differential value of soluble boron.
The invention also provides a method for pre-testing the shutdown date of the pressurized water reactor, which comprises the following steps: the reactor core monitoring system monitors the actually measured boron concentration daily to obtain the actually measured boron concentration Cmes(ii) a The measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000048
Calculating the average boron reduction rate v of the current month; calculating historical statistical average nuclear reactor power for respective time periods within a remaining life of a current cycle
Figure BDA0003021209970000049
The pressure water reactor shutdown date is predicted according to the following formula:
Figure BDA00030212099700000410
wherein T is predicted trip date, T0Is the current date, CEOLThe minimum operable boron concentration at the end of the life.
In one embodiment, the boron concentration C is measuredmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA00030212099700000411
The method comprises the following steps: moderator temperature effect, control rod position effect, Doppler power effect, xenon poisoning effect on measured state to reference stateBoron 10 abundance and samarium toxicity effect introduced correction factor delta rhomod、ΔρRCCA、Δρdop、ΔρXe、ΔCBB10And Δ ρSmThe measured boron concentration C is determined according to the following formulamesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000051
Figure BDA0003021209970000052
Wherein alpha isBIs the differential value of soluble boron.
The invention also provides a method for pre-testing the shutdown date of the pressurized water reactor, which comprises the following steps: the reactor core monitoring system monitors the actually measured boron concentration daily to obtain the actually measured boron concentration Cmes(ii) a The measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000053
Calculating the theoretical average boron reduction rate in the current cycle residual life
Figure BDA0003021209970000054
Calculating historical statistical average nuclear reactor power for respective time periods within a remaining life of a current cycle
Figure BDA0003021209970000055
The pressure water reactor shutdown date is predicted according to the following formula:
Figure BDA0003021209970000056
wherein T is predicted trip date, T0Is the current date, CEOLThe minimum operable boron concentration at the end of the life.
In one embodiment, the boron concentration C is measuredmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000057
The method comprises the following steps: to measureThe moderator temperature effect, control rod position effect, Doppler power effect and xenon poison effect of the quantity state to the reference state respectively introduce correction factors delta rhomod、ΔρRCCA、ΔρdopAnd Δ ρXeThe measured boron concentration C is determined according to the following formulamesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000058
Wherein alpha isBIs the differential value of soluble boron.
The invention also provides a method for pre-testing the shutdown date of the pressurized water reactor, which comprises the following steps: the reactor core monitoring system monitors the actually measured boron concentration daily to obtain the actually measured boron concentration Cmes(ii) a The measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000059
Calculating the theoretical average boron reduction rate in the current cycle residual life
Figure BDA00030212099700000510
Calculating historical statistical average nuclear reactor power for respective time periods within a remaining life of a current cycle
Figure BDA00030212099700000511
The pressure water reactor shutdown date is predicted according to the following formula:
Figure BDA00030212099700000512
wherein T is predicted trip date, T0Is the current date, CEOLThe minimum operable boron concentration at the end of the life.
In one embodiment, the boron concentration C is measuredmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA00030212099700000513
The method comprises the following steps: moderator temperature effect, control rod position effect, Doppler power for measuring state to reference stateCorrection factor delta rho introduced by effect, xenon poison effect, boron 10 abundance and samarium poison effectmod、ΔρRCCA、Δρdop、ΔρXe、ΔCBB10And Δ ρSmThe measured boron concentration C is determined according to the following formulamesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000061
Figure BDA0003021209970000062
Wherein alpha isBIs the differential value of soluble boron.
The invention has the beneficial technical effects that:
the method for predicting the shutdown date of a pressurized water reactor of the invention corrects the boron concentration
Figure BDA0003021209970000063
Adding correction to boron 10 abundance and samarium toxicity, and using theoretical average boron reduction rate in the remaining life of the current cycle
Figure BDA0003021209970000064
Replacing the current monthly average boron rate of decrease v, using historical statistical average nuclear reactor power over the remaining life for the corresponding time period
Figure BDA0003021209970000065
Substituted current monthly average nuclear reactor power PrThe prediction stability is high, and the result accuracy is relatively and greatly improved.
Drawings
FIG. 1 is a graph of the monthly boron decay rate as burn-up progresses;
FIG. 2 is a graph of measured average boron reduction rate as burn-up progresses over a remaining life;
FIG. 3 is a graph of theoretical average boron reduction rate as burnup progresses over a remaining life;
FIG. 4 is a comparison graph of the effect of predicting the annual refueling core shutdown date using the prior boron drop prediction method and the method of predicting the pressurized water reactor shutdown date provided in example 4, respectively;
FIG. 5 is a graph comparing the effect of predicting the long-cycle refueling core shutdown date using the prior boron drop prediction method and the method of predicting the pressurized water reactor shutdown date provided in example 4, respectively.
Detailed Description
Example 1
The existing boron drop prediction method comprises the following steps: the reactor core monitoring system monitors and measures the boron concentration daily to obtain the actually measured boron concentration Cmes(ii) a The measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA0003021209970000066
Calculating the average boron reduction rate v of the current month; calculating the current monthly average nuclear reactor power Pr(ii) a Predicting the shutdown date T of the pressurized water reactor according to the following formula:
Figure BDA0003021209970000067
wherein, T0Is the current date; cEOLThe minimum operable boron concentration at the end of life is in ppm, which is derived from the plant design and is typically 10 ppm.
The calculating the current monthly average boron reduction rate v comprises: the reactor core monitoring system monitors and measures the boron concentration daily to obtain the actually measured boron concentration at the bottom of the current month and the actually measured boron concentration at the bottom of the previous month; respectively correcting the boron concentration actually measured at the bottom of the current month and the boron concentration actually measured at the bottom of the previous month to the boron concentration in the reference state to obtain the corrected boron concentration at the bottom of the current month
Figure BDA0003021209970000071
And correcting boron concentration at the bottom of moon
Figure BDA0003021209970000072
Correcting boron concentration at the end of the month
Figure BDA0003021209970000073
And correcting boron concentration at the bottom of moon
Figure BDA0003021209970000074
The units are ppm; the reactor core monitoring system counts the actual fuel consumption at the bottom of the month
Figure BDA0003021209970000075
And the actual measured fuel consumption at the bottom of the previous month
Figure BDA0003021209970000076
Actual measured fuel consumption at the end of the month
Figure BDA0003021209970000077
And the actual measured fuel consumption at the bottom of the previous month
Figure BDA0003021209970000078
Units are equivalent full power day EFPD, and fuel consumption is actually measured at the end of the month
Figure BDA0003021209970000079
And the actual measured fuel consumption at the bottom of the previous month
Figure BDA00030212099700000710
The values are all between 0 and the design burnup; calculating the current monthly average boron reduction rate v according to the following formula:
Figure BDA00030212099700000711
the current monthly average boron reduction rate, v, is in ppm/EFPD.
The measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA00030212099700000712
The method comprises the following steps: introducing correction factors delta rho into the moderator temperature effect, control rod position effect, Doppler power effect and xenon poison effect from the measurement state to the reference state respectivelymod、ΔρRCCA、ΔρdopAnd Δ ρXeThe measured boron concentration C is determined according to the following formulamesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA00030212099700000713
Figure BDA00030212099700000714
Wherein alpha isBDifferential value of soluble boron, unit 10-5/(mg·kg-1)；Δρdop、Δρmod、ΔρRCCAAnd Δ ρXeAll units of (2) are 10-5。
The correction factor Δ ρmod、ΔρRCCA、ΔρdopAnd Δ ρXeObtained by the following steps:
Δρdop＝(Pref-Pmes)αdopwherein P isrefTo reference state power level, PmesThe measured power level of the reactor is expressed in% FP; alpha is alphadopThe Doppler power coefficient can be obtained by inquiring the nuclear design report of the power plant, and the unit is 10-5/％FP。
Figure BDA00030212099700000715
Wherein the content of the first and second substances,
Figure BDA00030212099700000716
for reference to the state of the average moderator temperature,
Figure BDA00030212099700000717
the average temperature of the actually measured moderator of the reactor is measured, and the unit is; alpha is alphamodThe temperature coefficient of the moderator can be obtained by inquiring the nuclear design report of a power plant, and the unit is 10-5/℃。
Figure BDA00030212099700000718
Wherein the content of the first and second substances,
Figure BDA00030212099700000719
for the corresponding reaction of the rod position of the reference state,
Figure BDA00030212099700000720
the reactivity corresponding to the actual measurement rod position can be obtained by inquiring the nuclear design report of the power plant, and the unit is 10-5。
Figure BDA0003021209970000081
Wherein the content of the first and second substances,
Figure BDA0003021209970000082
to balance the reactivity of xenon poison for the reference state,
Figure BDA0003021209970000083
for actually measuring the power to balance the reactivity of xenon poison, the nuclear design report of the power plant can be inquired for obtaining the power with the unit of 10-5。
The existing boron drop prediction method uses the current monthly average boron drop rate v. In fact, the time-dependent changes due to fissile nuclides and fission products are not linear over the lifetime. Referring to fig. 1, historical data is counted to obtain a graph of the change of the monthly average boron reduction rate v along with the deepening of the fuel consumption, and the change of the monthly average boron reduction rate v along with the fuel consumption is not stable at present. The result of the monthly average boron decay rate v prediction will necessarily fluctuate, especially at the beginning of life.
The existing boron drop prediction method uses the actually measured boron concentration CmesCorrected boron concentration obtained after correction
Figure BDA0003021209970000084
Introducing correction factors delta rho into the moderator temperature effect, control rod position effect, Doppler power effect and xenon poison effect from the measurement state to the reference state respectivelymod、ΔρRCCA、ΔρdopAnd Δ ρXeSamarium poisons and boron 10 abundance were not considered.
At the beginning of the cycle life, at least 40 days are needed for reaching the balance due to samarium toxin; and the plutonium production rate is greater than the consumption rate, and particularly in the fuel area at the beginning of the cycle life, the effect is more obvious. The two factors influence the linear change of the reactivity of the reactor core along with the burnup and the change of the boron reduction rate along with the burnup, and influence the extrapolation stop of the boron reduction prediction methodAccuracy of pile date. Meanwhile, as is well known, the boron element in nature is formed by boron 10: (10B) And boron 11: (11B) Two nuclides, and the natural abundance of boron 10 is 19.8%. Boron 10 is responsible for reactor control and boron 10 is constantly consumed during operation. Some nuclear power plants also have boron recovery systems, and the boron 10 abundance of the recovered boron must be less than the natural abundance. While the boric acid concentration analyzed by a chemical laboratory of a general power plant does not distinguish boron isotopes, including boron 10 and boron 11. Whether the boron 10 is normally consumed during power operation or the boron 10 abundance changes caused by power increase and decrease or new boric acid addition during shutdown, the accuracy of boron drop prediction extrapolation of shutdown date is affected if the boron 10 abundance is not corrected.
Example 2
This example provides a method of predicting a trip date for a pressurized water reactor which differs from the existing boron drop prediction method provided in example 1 in that the monthly average boron drop rate v is determined using the theoretical average boron drop rate over the remaining life of the current cycle
Figure BDA0003021209970000091
Instead.
Calculating the theoretical average boron reduction rate in the remaining life of the current cycle
Figure BDA0003021209970000092
The method comprises the following steps: calculating the current burn-up corresponding to the theoretical critical boron concentration
Figure BDA0003021209970000093
The unit is ppm, the burnup tracking calculation is carried out through a reactor core nuclear design program to obtain tracking data in the whole service life, generally from a nuclear power plant reactor core boron concentration tracking report, the corresponding theoretical critical boron concentration is found according to the current burnup, or the adjacent value is subjected to linear interpolation calculation, and the theoretical calculation needs to consider the abundance of boron 10; calculating theoretical fuel consumption of the reactor at the end of the cycle life
Figure BDA0003021209970000094
The unit EFPD is calculated by performing burnup tracking through a core design program to obtain the burnup at the minimum operable boron concentration (generally 10ppm), which is generally derived from core design reports, for example, the long fuel cycle of a 60-ten-thousand-kilowatt unit is generally about 480 EFPD; the reactor core monitoring system counts the actual fuel consumption at the bottom of the month
Figure BDA0003021209970000095
The unit equivalent full power day EFPD has a value generally between 0 and the designed fuel consumption; calculating the theoretical boron reduction rate in the current cycle residual life according to the following formula
Figure BDA0003021209970000096
The unit is ppm/EFPD.
The method provided by the embodiment uses the theoretical average boron reduction rate in the remaining life of the current cycle
Figure BDA0003021209970000097
Theoretically, as long as the accurate average boron reduction rate in the residual life of the fuel cycle can be obtained, the shutdown date can be predicted more accurately theoretically regardless of whether the change of the critical boron concentration along with the burnup is linear or not.
Referring to fig. 2, historical data is counted to obtain a trend graph of the average boron reduction rate along with the fuel consumption in the remaining life period. Comparing fig. 1 and fig. 2, it can be easily found that the latter has small fluctuation and better stability. Predicting the cycle life or the shutdown date in this way leads to results which are more stable and theoretically more accurate, in particular almost overlapping at the beginning of the life.
Calculating the average boron rate of decrease v' over the remaining life of the current cycle comprises: calculating the current burn-up corresponding to the theoretical critical boron concentration
Figure BDA0003021209970000098
The unit ppm generally comes from a tracking report of the concentration of boron designed in a reactor core, and the theoretical calculation needs to consider the abundance of boron 10; calculating the fuel consumption when the reactor is stopped at the end of the cycle life
Figure BDA0003021209970000101
The unit EFPD; the reactor core monitoring system counts the actual fuel consumption at the bottom of the month
Figure BDA0003021209970000102
The unit equivalent full power day EFPD has a value generally between 0 and the designed fuel consumption; the average boron reduction rate v' over the remaining lifetime is calculated according to the following equation:
Figure BDA0003021209970000103
the units ppm/EFPD.
In the practical process of core supervision, when the shutdown date prediction is required, the burnup at the shutdown end of the cycle life cannot be obtained
Figure BDA0003021209970000104
And therefore the average boron reduction rate v' for the remaining cycles in the lifetime cannot be obtained.
Burn-up at the end of the cycle life on the premise that the subcore design software is very mature
Figure BDA0003021209970000105
And theoretical burn-up at shutdown at end of cycle life
Figure BDA0003021209970000106
The deviation is very small and can be ignored, so the theoretical burn-up is generated when the reactor is stopped at the end of the cycle life
Figure BDA0003021209970000107
Can replace fuel consumption during shutdown at the end of the cycle life
Figure BDA0003021209970000108
From a comparison of FIGS. 2 and 3, the average boron rate of decay v' over the remaining lifetime is compared to the theoretical average boron rate of decay over the remaining lifetime
Figure BDA0003021209970000109
Over the life of the productConsistently, therefore, the theoretical average boron rate-of-fall over the remaining life of use
Figure BDA00030212099700001010
A method to predict the trip date is possible.
Example 3
This example provides a method of pre-pressuring a shutdown date of a pressurized water reactor, which is different from the method of pre-pressuring a shutdown date of a pressurized water reactor provided in example 2 in that a boron concentration is corrected
Figure BDA00030212099700001011
By correcting the boron concentration
Figure BDA00030212099700001012
Instead.
The measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA00030212099700001013
The method comprises the following steps: introducing correction factors delta rho into the moderator temperature effect, control rod position effect, Doppler power effect, xenon toxicity effect, boron 10 abundance and samarium toxicity effect from the measurement state to the reference state respectivelymod、ΔρRCCA、Δρdop、ΔρXe、ΔCBB10And Δ ρSmThe measured boron concentration C is determined according to the following formulamesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure BDA00030212099700001014
Figure BDA00030212099700001015
Wherein alpha isBDifferential value of soluble boron, unit 10-5/(mg·kg-1)；Δρdop、Δρmod、ΔρRCCA、ΔρXeAnd ΔρSmThe units are all 10-5，ΔCBB10The unit is: mg, kg-1。
The correction factor Δ ρmod、ΔρRCCA、Δρdop、ΔρXe、ΔρSmAnd Δ CBB10Δ ρ is obtained by the following methods, respectivelydop＝(Pref-Pmes)αdopWherein P isrefTo reference state power level, PmesThe measured power level of the reactor is expressed in% FP; alpha is alphadopThe Doppler power coefficient can be obtained by inquiring the nuclear design report of the power plant, and the unit is 10-5/％FP。
Figure BDA0003021209970000111
Wherein the content of the first and second substances,
Figure BDA0003021209970000112
for reference to the state of the average moderator temperature,
Figure BDA0003021209970000113
the average temperature of the actually measured moderator of the reactor is measured, and the unit is; alpha is alphamodThe temperature coefficient of the moderator can be obtained by inquiring the nuclear design report of a power plant, and the unit is 10-5/℃。
Figure BDA0003021209970000114
Wherein the content of the first and second substances,
Figure BDA0003021209970000115
for the corresponding reaction of the rod position of the reference state,
Figure BDA0003021209970000116
the reactivity corresponding to the actual measurement rod position can be obtained by inquiring the nuclear design report of the power plant, and the unit is 10-5。
Figure BDA0003021209970000117
Wherein the content of the first and second substances,
Figure BDA0003021209970000118
to balance the reactivity of xenon poison for the reference state,
Figure BDA0003021209970000119
for actually measuring the power to balance the reactivity of xenon poison, the nuclear design report of the power plant can be inquired for obtaining the power with the unit of 10-5。
Figure BDA00030212099700001110
Wherein the content of the first and second substances,
Figure BDA00030212099700001111
to balance the reactivity of the samarium toxin for the reference state,
Figure BDA00030212099700001112
for actually measuring the reactivity of the power balance samarium toxin, the reactivity can be obtained by inquiring a nuclear design report of a power plant, and the unit is 10-5。
Figure BDA00030212099700001113
Wherein, CmesFor actually measuring the boron concentration, the unit mg.kg-1；AB10RAs a practical matter in the core coolant10B abundance, unit%; a. theB10DFor use in core design10B abundance, unit%.
In the method provided in this example, the boron concentration is corrected
Figure BDA00030212099700001114
Is to measure the actually measured boron concentration CmesRespectively introducing correction factors delta rho to the moderator temperature effect, the control rod position effect, the Doppler power effect, the xenon poison effect, the samarium poison effect and the boron 10 abundance from the measurement state to the reference state after correctionmod、ΔρRCCA、Δρdop、ΔρXe、ΔρSmAnd Δ CBB10. Correcting boron concentration
Figure BDA00030212099700001115
The correction of boron 10 abundance and samarium toxic effect is increased, and the accuracy of the prediction of the shutdown date of the pressurized water reactor is improved.
Example 4
This embodiment provides a method for pre-measuring a shutdown date of a pressurized water reactor, which is different from the method for pre-measuring a shutdown date of a pressurized water reactor provided in embodiment 3 in that the average nuclear reactor power P is currently measuredrUsing historical statistical average nuclear reactor power for corresponding time periods within the remaining life of the current cycle
Figure BDA0003021209970000121
Instead. For a unit which has been operated for more than a complete calendar year, a complete set of numerical values or curves of power changing along with seasons are obtained by counting the power level of each day under the normal working condition of the unit, and the complete set of numerical values or curves are used for calculating historical statistical average nuclear reactor power of response time periods in the rest first period
Figure BDA0003021209970000122
The method provided by the embodiment uses historical statistical average nuclear reactor power of corresponding time periods in remaining life
Figure BDA0003021209970000123
In the operation process of a nuclear power plant, the power generation efficiency of the two-loop turbine generator can be changed along with the change of seasonal air temperature, and in order to maintain the power of the two-loop turbine generator unchanged, the power of the reactor of the primary loop can be changed along with the seasonal air temperature, so that the historical statistics of the corresponding time period in the remaining service life is used for averaging the power of the nuclear reactor
Figure BDA0003021209970000124
To predict that the trip date is more realistic.
Example 5
Referring to fig. 4 and 5, the annual refueling core/long-cycle refueling core shutdown date is predicted by using the boron drop prediction method provided in example 1 and the method for predicting the long-cycle refueling core shutdown date provided in example 4 respectively, and the method for predicting the long-cycle refueling core shutdown date provided in example 4 is verified through historical data to predict a very accurate result in terms of the life time, wherein the result predicted by the method for predicting the long-cycle refueling core shutdown date provided in example 4 is more stable and accurate no matter whether the annual refueling core shutdown date or the long-cycle refueling core shutdown date is predicted.
Examples 2-4 provide a method of predicting reactor shutdown dates for pressurized water reactors that is equally applicable to other nuclear power plant reactor shutdown date predictions.
The above-mentioned embodiments only express several embodiments of the present invention, and the description thereof is more specific and detailed, but not construed as limiting the scope of the present invention. It should be noted that, for a person skilled in the art, several variations and modifications can be made without departing from the inventive concept, which falls within the scope of the present invention. Therefore, the protection scope of the present patent shall be subject to the appended claims.

Claims (12)

1. A method of pre-staging the shutdown date of a pressurized water reactor, comprising the steps of: the reactor core monitoring system monitors the actually measured boron concentration daily to obtain the actually measured boron concentration Cmes(ii) a The measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure FDA0003021209960000011
Calculating the theoretical average boron reduction rate in the current cycle residual life
Figure FDA0003021209960000012
Calculating the current monthly average nuclear reactor power Pr(ii) a The pressure water reactor shutdown date is predicted according to the following formula:
Figure FDA0003021209960000013
wherein T is predicted trip date, T0Is the current date, CEOLThe minimum operable boron concentration at the end of the life.
2. The method of prepressing water reactor shut-down date according to claim 1, wherein a theoretical average boron rate-of-fall over a remaining life of a current cycle is calculated
Figure FDA0003021209960000014
The method comprises the following steps: calculating the current burn-up corresponding to the theoretical critical boron concentration
Figure FDA0003021209960000015
The core monitoring system counts the current actual fuel consumption
Figure FDA0003021209960000016
Calculating theoretical fuel consumption of the reactor at the end of the cycle life
Figure FDA0003021209960000017
Calculating the theoretical average boron reduction rate in the residual service life of the current cycle according to the following formula
Figure FDA0003021209960000018
Figure FDA0003021209960000019
3. A method of pre-staging the shutdown date of a pressurized water reactor, comprising the steps of: the reactor core monitoring system monitors the actually measured boron concentration daily to obtain the actually measured boron concentration Cmes(ii) a The measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure FDA00030212099600000110
Calculating the average boron reduction rate v of the current month(ii) a Calculating the current monthly average nuclear reactor power Pr(ii) a The pressure water reactor shutdown date is predicted according to the following formula:
Figure FDA00030212099600000111
wherein T is predicted trip date, T0Is the current date, CEOLThe minimum operable boron concentration at the end of the life.
4. Method for forecasting shut-down dates for pressurized water reactor according to claim 3, characterized in that the measured boron concentration C is measuredmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure FDA00030212099600000112
The method comprises the following steps: introducing correction factors delta rho for moderator temperature effect, control rod position effect, Doppler power effect, xenon toxicity effect, boron 10 abundance and samarium toxicity effect from measurement state to reference statemod、ΔρRCCA、Δρdop、ΔρXe、ΔCBB10And Δ ρSmThe measured boron concentration C is determined according to the following formulamesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure FDA00030212099600000113
Figure FDA00030212099600000114
Wherein alpha isBIs the differential value of soluble boron.
5. A method of pre-staging the shutdown date of a pressurized water reactor, comprising the steps of: the reactor core monitoring system monitors the actually measured boron concentration daily to obtain the actually measured boron concentration Cmes(ii) a The measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure FDA0003021209960000021
Calculating the average boron reduction rate v of the current month; calculating historical statistical average nuclear reactor power for respective time periods within a remaining life of a current cycle
Figure FDA0003021209960000022
The pressure water reactor shutdown date is predicted according to the following formula:
Figure FDA0003021209960000023
wherein T is predicted trip date, T0Is the current date, CEOLThe minimum operable boron concentration at the end of the life.
6. A method of pre-staging the shutdown date of a pressurized water reactor, comprising the steps of: the reactor core monitoring system monitors the actually measured boron concentration daily to obtain the actually measured boron concentration Cmes(ii) a The measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure FDA0003021209960000024
Calculating the theoretical average boron reduction rate in the current cycle residual life
Figure FDA0003021209960000025
Calculating the current monthly average nuclear reactor power Pr(ii) a The pressure water reactor shutdown date is predicted according to the following formula:
Figure FDA0003021209960000026
wherein T is predicted trip date, T0Is the current date, CEOLThe minimum operable boron concentration at the end of the life.
7. The method of pre-pressure pwr shut-down date according to claim 6, characterized in that the measured boron concentration C is measuredmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure FDA0003021209960000027
The method comprises the following steps: introducing correction factors delta rho for moderator temperature effect, control rod position effect, Doppler power effect, xenon toxicity effect, boron 10 abundance and samarium toxicity effect from measurement state to reference statemod、ΔρRCCA、Δρdop、ΔρXe、ΔCBB10And Δ ρSmThe measured boron concentration C is determined according to the following formulamesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure FDA0003021209960000028
Figure FDA0003021209960000029
Wherein alpha isBIs the differential value of soluble boron.
8. A method of pre-staging the shutdown date of a pressurized water reactor, comprising the steps of: the reactor core monitoring system monitors the actually measured boron concentration daily to obtain the actually measured boron concentration Cmes(ii) a The measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure FDA00030212099600000210
Calculating the average boron reduction rate v of the current month; calculating historical statistical average nuclear reactor power for respective time periods within a remaining life of a current cycle
Figure FDA0003021209960000031
The pressure water reactor shutdown date is predicted according to the following formula:
Figure FDA0003021209960000032
wherein T is predicted trip date, T0Is the current date, CEOLThe minimum operable boron concentration at the end of the life.
9. The method of prepressing shutdown date for a pressurized water reactor of claim 8, and othersCharacterized in that the measured boron concentration C ismesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure FDA0003021209960000033
The method comprises the following steps: introducing correction factors delta rho for moderator temperature effect, control rod position effect, Doppler power effect, xenon toxicity effect, boron 10 abundance and samarium toxicity effect from measurement state to reference statemod、ΔρRCCA、Δρdop、ΔρXe、ΔCBB10And Δ ρSmThe measured boron concentration C is determined according to the following formulamesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure FDA0003021209960000034
Figure FDA0003021209960000035
Wherein alpha isBIs the differential value of soluble boron.
10. A method of pre-staging the shutdown date of a pressurized water reactor, comprising the steps of: the reactor core monitoring system monitors the actually measured boron concentration daily to obtain the actually measured boron concentration Cmes(ii) a The measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure FDA0003021209960000036
Calculating the theoretical average boron reduction rate in the current cycle residual life
Figure FDA0003021209960000037
Calculating historical statistical average nuclear reactor power for respective time periods within a remaining life of a current cycle
Figure FDA0003021209960000038
The pressure water reactor shutdown date is predicted according to the following formula:
Figure FDA0003021209960000039
wherein T is predicted trip date, T0Is the current date, CEOLThe minimum operable boron concentration at the end of the life.
11. A method of pre-staging the shutdown date of a pressurized water reactor, comprising the steps of: the reactor core monitoring system monitors the actually measured boron concentration daily to obtain the actually measured boron concentration Cmes(ii) a The measured boron concentration CmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure FDA00030212099600000310
Calculating the theoretical average boron reduction rate in the current cycle residual life
Figure FDA00030212099600000311
Calculating historical statistical average nuclear reactor power for respective time periods within a remaining life of a current cycle
Figure FDA00030212099600000312
The pressure water reactor shutdown date is predicted according to the following formula:
Figure FDA00030212099600000313
wherein T is predicted trip date, T0Is the current date, CEOLThe minimum operable boron concentration at the end of the life.
12. The method of predicting shutdown date of a pressurized water reactor of claim 11, wherein the measured boron concentration C is measuredmesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure FDA0003021209960000041
The method comprises the following steps: moderator temperature effect, control rod position effect, Doppler power effect, xenon poisoning effect, boron 10 abundance, and samarium poisoning effect on measured to reference statesIntroducing a correction factor Δ ρmod、ΔρRCCA、Δρdop、ΔρXe、ΔCBB10And Δ ρSmThe measured boron concentration C is determined according to the following formulamesCorrecting the boron concentration in the reference state to obtain a corrected boron concentration
Figure FDA0003021209960000042
Figure FDA0003021209960000043
Wherein alpha isBIs the differential value of soluble boron.
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