CN104036837A - Fluxgraph time and continuous time reactor core monitoring power uncertainty analysis method - Google Patents
Fluxgraph time and continuous time reactor core monitoring power uncertainty analysis method Download PDFInfo
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Abstract
The invention discloses a fluxgraph time reactor core monitoring power uncertainty analysis method. The method comprises the following steps: configuring a fluxgraph theoretical state; configuring a fluxgraph turbulent state; configuring theoretical measurement data of hardware; generating new measurement data by increasing the uncertainty of the measurement hardware; obtaining a reconfiguration state of the fluxgraph; determining the general uncertainty of the monitoring power distribution of the fluxgraph measurement time reactor core according to the fluxgraph turbulent state and fluxgraph reconfiguration state. Compared with the prior art, when the general uncertainty is determined, each uncertainty factory does not need to be considered and analyzed one by one, the error of the general uncertainty quantity can be reduced under the situation that the relative independence of each uncertainty factory is weakened, a foundation is set for the reliability and engineering application of the reactor core monitoring system, the running controllability and safety of the reactor core can be improved, the thermal margin is released, and the economical performance of a power plant can be improved. The invention also discloses a continuous time reactor core monitoring power uncertainty analysis method.
Description
Technical field
The present invention relates to nuclear reactor power distribution technology field, relate more specifically to a kind of flux pattern constantly and the continuous monitoring of nuclear reactor constantly power Uncertainty Analysis Method.
Background technology
Conventionally, in nuclear reactor operational process, need the three-dimensional power of regularly monitoring heap in-core to distribute (or real-time online), analyze the uncertainty that core power distributes, to verify operation controllability and the security of reactor core.
Please refer to document " US-APWR Incore Power Distribution Evaluation Methodology.MUAP-07021-NP (R0) (Non-Proprietary Version); December2007 ", the uncertainty analysis distributing about core power, according to the physical process of flux pattern In-core Instrumentation, the overall uncertainty that power is distributed is divided into following component:
Wherein:
represent the uncertainty that local rod power distributes
represent to measure the uncertainty that activity is converted to the process introducing of measuring power
represent to measure power and derive from measurement point the uncertainty that non-measurement point is introduced
characterize the uncertainty of measurement data itself
According to the concrete meaning of each component, analyze item by item.Wherein
depend on the precision of the excellent power reconstructed module of theoretical reactor core predictor (as reactor core joint piece method program),
depend on theoretical prediction program and from measuring activity, be converted to the precision of the conversion coefficient of measuring power.
and
need, according to on-the-spot actual physics measurement data, to analyse item by item, then carry out overall probabilistic definite.
In said method, in the uncertainty analysis that core power is distributed, related component (comprises uncertain component
) consider item by item, analyze, make error larger, thereby be difficult to provide basis for reliability and the engineering application of reactor core monitoring system.
In addition, in order to improve controllability and the security of reactor core operation, also need the uncertainty that continuous moment reactor core monitoring power is distributed to analyze.
Summary of the invention
The method that the object of this invention is to provide the uncertainty analysis of a kind of flux pattern nuclear reactor monitoring constantly power, the method is when determining overall uncertain amount, do not need to consider item by item, analyze each uncertain component, to reduce this overall uncertain error of measuring in the situation that the relative independentability of each uncertain component weakens, for the reliability of reactor core monitoring system and engineering application provide basis, improve controllability and the security of reactor core operation.
Another object of the present invention is to provide the method for a kind of continuous moment nuclear reactor monitoring power uncertainty analysis, to improve controllability and the security of reactor core operation.
For achieving the above object, the invention provides the method for a kind of flux pattern nuclear reactor monitoring constantly power uncertainty analysis, comprising:
(1) the theoretical state of theoretical reactor core parametric configuration flux pattern of inscribing while measuring according to reactor core flux pattern;
(2) when flux pattern is measured, inscribe at least one parameter of theoretical reactor core parameter is carried out to disturbance, to construct flux pattern disturbance state;
(3) according to the physical characteristics of flux pattern disturbance state and measurement hardware, the theoretical measurement data of structure hardware;
(4) the theoretical measurement data increase in (3) is respectively measured to the uncertainty of hardware, to produce new measurement data, new measurement data comprises the new measurement data of EXCORE, the new measurement data of T/C, TIP or the new measurement data of SPD;
(5) by the data input processing software under TIP or the new measurement data of SPD and the theoretical state of flux pattern, obtain flux pattern reconstruct state;
(6) according to flux pattern disturbance state and flux pattern reconstruct state, determine total uncertainty that flux pattern measurement reactor core monitoring constantly power distributes.
Compared with prior art, method of the present invention is from the theoretical state of structure flux pattern, at flux pattern, constantly theoretical reactor core parameter is carried out to error disturbance with structure flux pattern disturbance state, in the situation that there is no measurement data, according to operating experience and each, measure the physical principle characteristic of hardware, constructed the theoretical measurement data of hardware, and the uncertainty of measuring hardware by theoretical measurement data stack is to produce new measurement data (having simulated actual measurement data), according to the theoretical state of flux pattern and new measurement data, obtain flux pattern reconstruct state again, finally according to flux pattern disturbance state and reconstruct state, determine the uncertainty that flux pattern reactor core monitoring constantly power distributes, , the method is when determining overall uncertain amount, do not need to consider item by item, analyze each uncertain component, in the situation that the relative independentability of each uncertain component weakens the error that has reduced this overall uncertain amount, for the reliability of reactor core monitoring system and engineering application provide the foundation, the controllability and the security that have improved reactor core operation, discharged thermal technology's allowance, improved power station economy.
Particularly, theoretical reactor core parameter comprises boron CONCENTRATION DISTRIBUTION deviation, control rod rod position step-out deviation, radially power distribution bias, axial power distribution bias, Xenon transient state and burnup profile deviation.
Particularly, measure hardware and comprise packaged type detection system (RIC/TIP) in heap, heap internally-fixed detection system (RIC/FID), core temperature measuring system (T/C), out-pile Nuclear measurement system (EXCORE).
Particularly, the theoretical measurement data in step (3) comprises the theoretical measurement data of EXCORE ex-core detector, the theoretical measurement data of detector in the theoretical measurement data of T/C thermopair, the interior detector of TIP packaged type heap or the fixed heap of SPD.
Particularly, the theoretical measurement data of structure EXCORE ex-core detector specifically comprises:
Under flux pattern disturbance state, by reactor core Nodal, calculate three-dimensional Flux Distribution φ (i, j, k) in structure heap, and in conjunction with the heap of three-dimensional (or two dimension adds one dimension) interior-out-pile response matrix W (i, j, k, m) calculates.
Particularly, the theoretical measurement data of structure T/C thermopair specifically comprises:
Under flux pattern disturbance state, determine near the power data coolant channel at T/C thermopair place, and the enthalpy that power data is converted into T/C coolant channel is risen to H
deldata;
According to the coolant inlet temperature T of reactor core name
in, coolant pressure P, by cooling medium physical property, calculate coolant entrance enthalpy H
in;
According to entrance enthalpy H
inand enthalpy rises H
delobtain exporting enthalpy H
out:
H
out＝H
in+H
del；
According to coolant pressure P and outlet enthalpy H
outobtain coolant temperature:
T
out=f (H
out, P), wherein f is the physical property function that cooling medium is relevant.
Particularly, in structure TIP packaged type heap, the theoretical measurement data of detector specifically comprises:
Fission reaction cross-sectional distribution (the ∑ of the physics macroscopic view (or microcosmic) of the calculative determination TIP probe by Nodal method under flux pattern disturbance state
f1and ∑
f2), and the Flux Distribution (φ of definite TIP probe positions
1and φ
2), by calculating the fission reaction rate RR of TIP, obtain, wherein RR=φ
1* ∑
f1+ φ
2* ∑
f2.
Correspondingly, the present invention also provides the method for a kind of continuous moment nuclear reactor monitoring power uncertainty analysis, comprising:
(1) at consecutive hours, inscribe at least one parameter of reactor core theoretical parameter is carried out to disturbance, to construct continuous disturbance state;
(2), according to the physical characteristics of continuous disturbance state and measurement hardware, construct the theoretical measurement data of hardware under continuous disturbance state;
(3) the theoretical measurement data increase in (2) is respectively measured to the uncertainty of hardware, to produce new measurement data;
(4) according to the new measurement data in (3) and demarcation relation, obtain the power of reactor core monitoring constantly continuously and distribute, wherein demarcation relation characterizes precision lower but the measurement hardware of continuous coverage and the corresponding relation that flux pattern is measured power distribution results constantly;
(5) according to continuous disturbance state and the distribution of the continuous monitoring of reactor core constantly power, determine the uncertainty that on-line continuous moment reactor core monitoring power distributes.
Compared with prior art, method of the present invention has realized the probabilistic analysis of continuous moment reactor core monitoring power, introduce in the method hardware and demarcated analog computation (demarcation relation), realized from flux pattern constantly core power distribute overall uncertainty analysis flow process to the distribute transformation of overall uncertainty analysis flow process of continuous moment reactor core monitoring power, can simulate the many demarcating steps of long time period (in burnup circulation) (as a plurality of flux patterns are demarcated) and more complicated hardware system and (comprise TIP/SPD, EXCORE, TC etc.) observation process, thereby can improve controllability and the security of reactor core operation, discharged thermal technology's allowance, improved power station economy.
During particularly, according to flux pattern, inscribe produced new measurement data and flux pattern reconstruct state is determined demarcation relation.
Particularly, inscribe detailed process that new measurement data and flux pattern reconstruct state produce during flux pattern as mentioned above.
By following description also by reference to the accompanying drawings, it is more clear that the present invention will become, and these accompanying drawings are used for explaining embodiments of the invention.
Accompanying drawing explanation
Fig. 1 is the process flow diagram of the method for flux pattern of the present invention nuclear reactor monitoring constantly power uncertainty analysis.
Fig. 2 is the present invention's process flow diagram of the method for the power of nuclear reactor monitoring constantly uncertainty analysis continuously.
Embodiment
With reference now to accompanying drawing, describe embodiments of the invention, in accompanying drawing, similarly element numbers represents similar element.
The invention belongs to other nuclear power station reactor core monitoring system field of 30～2,000,000 kilowatts (electric power) level, applicable comprise when the first two generation add nuclear power station LOCA nargin monitoring system (LSS), three generations adds the three-dimensional on-line monitoring system of nuclear power station (as AP1000 and EPR) reactor core (OMS) etc.
Please refer to Fig. 1, the method for flux pattern of the present invention nuclear reactor monitoring constantly power uncertainty analysis mainly comprises:
S101, the theoretical state of theoretical reactor core parametric configuration flux pattern of inscribing while measuring according to reactor core flux pattern.
S102 inscribes at least one parameter of theoretical reactor core parameter is carried out to disturbance when flux pattern is measured, to construct flux pattern disturbance state.
In new operation reactor and instrument, owing to lacking operating measurement data, therefore can obtain by reference to the measured data of instrument the difference of actual reactor core and Theoretical Design reactor core.As the measurement result of the presurized water reactor RIC system of current domestic main flow, can be used for defining the difference of actual reactor core and theoretical reactor core.Therefore, the actual reactor core that the present invention determines according to reference meter under flux pattern and the deviation of theoretical reactor core, structure disturbance reactor core represents actual reactor core.
Particularly, the present invention is when the difference of the actual reactor core of definition and theoretical reactor core, and available at least one parameter to theoretical reactor core parameter is carried out disturbance, to construct disturbance reactor core, represents actual reactor core, realizes the simulation of reactor core virtual condition.Wherein, excitation parameter can be current reactor core state representation amount, as boron concentration (boracic presurized water reactor), boron CONCENTRATION DISTRIBUTION deviation, control rod rod position step-out deviation, or be power distribution shape running parameter (as radially power distribution bias, axial power distribution bias, Xenon transient state), can be also reactor core burnup history run parameter (as burnup profile deviation, nucleon distribution density).
In fact, the present embodiment starts from the flux pattern theoretical model state of reactor core, and according to the long-time running data of flux pattern and the support of experience, structure, corresponding to the Disturbance Model of theory state, is called flux pattern disturbance state.
Flux pattern long-time running data have comprised the measured value that the real power of a large amount of actual reactor cores distributes, and the deviation of the calculated value of this measured value and reactor core Theoretical Design has characterized actual core power and distributed and the difference degree that designs core power distribution.The present invention carries out statistical study by the power distribution bias of measured value and design load, and definite power distribution bias source and inclined to one side extent.From the running technology standard of reactor core operation with can affect in theory the influence factor of reactor core operation, the present invention is converted to the deviation of power distribution the parameter perturbation of a series of reactor core parameter characterizations, and definite parameter perturbation amplitude.Particularly, by measurement and the deviation of the power distribution of Theoretical Design, be converted to the deviation of reactor core parameter perturbation, conventionally, by the restrictive condition of a large amount of operating experience and power plant's actual motion, through evaluating, calculate.And parameter perturbation amplitude, the experimental data base of actual motion of take is basis, through evaluating, calculating.
S103, according to the physical characteristics of flux pattern disturbance state and measurement hardware, the theoretical measurement data of structure hardware.Wherein, measure hardware and comprise packaged type detection system (RIC/TIP) in heap, heap internally-fixed detection system (RIC/FID), core temperature measuring system (T/C), out-pile Nuclear measurement system (EXCORE).
In the present invention from flux pattern disturbance state, construct the theoretical measurement data of each reactor core hardware condition, comprise the theoretical measurement data of EXCORE ex-core detector, the theoretical measurement data of detector in the theoretical measurement data of T/C thermopair, the interior detector of TIP packaged type heap or the fixed heap of SPD.Particularly, the calculating of theoretical measurement data in the present invention, the reactor core state while putting into reactor core according to hardware and the physical characteristics principle of hardware itself obtain.
Particularly, the detailed process of structural theory measurement data is as follows:
(1) the theoretical measurement data of EXCORE ex-core detector
According to physical characteristics, and the meticulous power of three-dimensional or flux in the reading of EXCORE derives from and piles (as fast group flux φ (i, j, k), i, j, the coordinate of the specifiable lattice in k corresponding three-dimensional space.In heap, generally in x-y plane, be divided into NX*NY grid, in Z direction, be divided into NZ grid), through Neutron Transport Theory, arriving the flux of ex-core detector position and the material of EXCORE can react, and generation current.In heap, neutron flux arrives the process of ex-core detector generation current through Neutron Transport Theory, can simulate by the widely used shielding of industry or Monte Carlo Calculation software (as MCNP) etc., and calculate the corresponding relation of three-dimensional power (or flux) and ex-core detector in heap, response matrix W (the i that is called out-pile in heap, j, k, m), i wherein, j, k is the coordinate of a certain grid in three dimensions in heap, and m is for some concrete ex-core detectors (or detector sensitive segment).
Therefore in the present invention, the theoretical measurement data of EXCORE ex-core detector, is expressed as C
prd(m), can be from reactor core flux pattern disturbance state, by reactor core Nodal, calculate three-dimensional flux (or power) distribution phi (i in (as commercial ANC, SMART, SIMULATE constant pitch piece program) structure heap, j, k), in the heap and in conjunction with three-dimensional (or two dimension adds one dimension)-out-pile response matrix W (i, j, k, m) by calculating.
(2) the theoretical measurement data of T/C thermopair
According to physical characteristics, the reading of T/C thermopair has characterized the temperature of the reactor coolant of core exit T/C position, and coolant outlet temperature, the enthalpy of the cooling medium causing to temperature in and the heating in this passage of coolant channel rises relevant.The enthalpy of cooling medium rises simultaneously also proportional with near the power of fuel coolant channel.
Therefore in the present invention, the theoretical measurement data of T/C thermopair, can determine near the power data of coolant channel at T/C thermopair place from reactor core flux pattern disturbance state, and the enthalpy that is converted into T/C coolant channel rises H
deldata.According to the coolant inlet temperature T of reactor core name (specified)
in, coolant pressure P, can be by cooling medium physical property calculate coolant entrance enthalpy H
in.The physical property table of cooling medium, refers to the corresponding relation table of the temperature, pressure, enthalpy, vaporization, liquefaction etc. of cooling medium).According to entrance enthalpy and enthalpy liter, can calculate outlet enthalpy.
H
out＝H
in+H
del
Enthalpy H at setting pressure P and cooling medium
out, calculate coolant temperature.
T
out＝f(H
out,P)
Wherein f is the physical property function that cooling medium is relevant.
(3) the theoretical measurement data of detector in TIP packaged type heap
According to physical characteristics, the reading of the interior detector of TIP packaged type heap derives from the flux of TIP position in heap and (comprises fast group φ
1and heat group φ
2) there is fission reaction and then generation current reading with the susceptibility material (as U235) of TIP probe.This current indication is directly proportional to the fission reaction rate of TIP position, and the fission reaction cross section of the material of fission reaction rate and TIP probe (comprises fast group's fission cross section ∑
f1and heat group fission cross section ∑
f2) and the flux level (φ of TIP probe positions
1and φ
2) relevant.
Therefore in the present invention, the theoretical measurement data of TIP packaged type detector, can, from the disturbance of reactor core flux pattern, by the calculating (as commercial ANC, SMART, SIMULATE constant pitch piece program) of Nodal method, determine the fission reaction cross-sectional distribution (∑ of the physics macroscopic view (or microcosmic) of TIP probe
f1and ∑
f2), and the Flux Distribution (φ of definite TIP probe positions
1and φ
2), by calculating the fission reaction rate RR of TIP, obtain.
RR＝φ
1×∑
f1+φ
2×∑
f2
(4) the theoretical measurement data of detector in the fixed heap of SPD
According to physical characteristics, in the fixed heap of SPD, the measurement electric current of detector derives from the absorption reaction effect of flux and the SPD probe susceptibility of SPD position in heap, generation current after the absorption extremely of the electronics sending arrival SPD.
So in the present invention, the theoretical measurement data production process of SPD stationary detector, similar with the theoretical measurement data of TIP packaged type detector, reaction type and mechanism that electric current still occurs are slightly different.
S104, respectively measures the uncertainty of hardware, to produce new measurement data to the theoretical measurement data increase in S103.
Any reactor core hard ware measure all can have the uncertainty of measurement.In the present invention, for the theoretical measurement data of EXCORE, the theoretical measurement data of T/C, TIP or the theoretical measurement data of SPD, increase the uncertainty of respectively measuring hardware, produce respectively new measurement data, measurement data as new in EXCORE, the new measurement data of T/C, TIP or the new measurement data of SPD.It should be noted that, the precision of different hardware systems and uncertain different is measured power precision than T/C high as the precision that TIP measures power.
Particularly, in the present invention by theoretical measurement data C
prdto new measurement data C
mesprocess, the introducing by the given different measuring probabilistic stochastic error relevant to different hardware realizes.
C
mes＝C
prd×(1+δ)
Measuring uncertainty has characterized measured value and has obeyed the random variation planting under the 95%-95% confidence level situation of dividing just very much.Therefore in the present invention, δ is according to the concept of measuring uncertainty, and the mode by random sampling calculates.For the difference of time of different hard ware measure uncertainties and random sampling, δ is different.For embodying the just too Distribution Effect of δ sampling, the present invention has repeated this simulation process in a large number.
S105, the data input processing software by under TIP or the new measurement data of SPD and the theoretical state of flux pattern, obtains flux pattern reconstruct state.
The hardware of TIP and SPD has represented the high-precision measurement hardware of In-core Instrumentation at present.In flux pattern software processing procedure in the present invention, the data of usining under the theoretical state of high-precision hard ware measure data (as TIP or SPD measurement data) and corresponding reactor core flux pattern are inputted as software, and the three-dimensional power can output flow figure reconstruct obtaining distributes.The three-dimensional power that this reconstruct is obtained distributes, and is called flux pattern reconstruct state.
It should be noted that, in the present invention, the current indication that the reaction rate (comprising fission or absorption reaction) of the detector characterizing due to TIP or the new measurement data of SPD causes, need to process new measurement data by flux pattern software.In flux pattern process software, utilize power that the theoretical state of flux pattern provides and the ratio of reaction rate, measurement data is converted to the power data of measurement.Because TIP or SPD measurement data have only covered the few measured zone of reactor core, therefore utilize flux pattern process software, the power providing in conjunction with the theoretical state of flux pattern distributes, by the power data of measuring, expanding into the three-dimensional power of full heap distributes, the three-dimensional power that is called reconstruct distributes, i.e. flux pattern reconstruct state in the present invention.
S106, determines according to flux pattern disturbance state and flux pattern reconstruct state total uncertainty that flux pattern measurement reactor core monitoring constantly power distributes.
In the present invention, according to the core power of flux pattern reconstruct state, distribute and disturb the variation between dynamic core power distribution with respect to the flux pattern that represents reactor core virtual condition, computational analysis obtains total uncertainty that flux pattern monitoring core power distributes.
Because the power of reconstruct state distributes and disturbs dynamic power and distribute and be the normalized distribution of reactor core.By the definite reactor core deviation profile of two normalized distributions of reactor core, the angle of probability statistics, obedience standard just too distributes, and the 95%-95% fiducial interval that therefore distributes just very much definite by this is total uncertainty that flux pattern monitoring core power distributes.
Compared with prior art, method of the present invention is from the theoretical state of structure flux pattern, at flux pattern, constantly theoretical reactor core parameter is carried out to error disturbance with structure flux pattern disturbance state, in the situation that there is no measurement data, according to operating experience and each, measure the physical principle characteristic of hardware, constructed the theoretical measurement data of hardware, and the uncertainty of measuring hardware by theoretical measurement data stack is to produce new measurement data (having simulated actual measurement data), according to the theoretical state of flux pattern and new measurement data, obtain flux pattern reconstruct state again, finally according to flux pattern disturbance state and reconstruct state, determine the uncertainty that flux pattern reactor core monitoring constantly power distributes, , the method is when determining overall uncertain amount, do not need to consider item by item, analyze each uncertain component, in the situation that the relative independentability of each uncertain component weakens the error that has reduced this overall uncertain amount, for the reliability of reactor core monitoring system and engineering application provide the foundation, the controllability and the security that have improved reactor core operation, discharged thermal technology's allowance, improved power station economy.
Please refer to Fig. 2, the present invention also provides the method for a kind of continuous moment nuclear reactor monitoring power uncertainty analysis again.
It should be noted that, in the present invention due to more high-precision measurement hardware system (as TIP system) can not be continuously real-time carry out reactor core monitoring, therefore need that reactor core precision is lower but continuous coverage support hardware (as EXCORE and T/C) provides the measurement data source of reactor core on-line continuous monitoring.The present invention is according to the reconstruction calculations of flux pattern software, sets up with high precision more but the relation that the three-dimensional power of discontinuous hard ware measure institute reconstruct distributes respectively for the hardware of respectively measuring of continuous monitoring, and the process of establishing for this corresponding relation, is called calibrated and calculated.In the present invention, according to the new measurement data of the EXCORE in Fig. 1 and flux pattern reconstruct state, set up EXCORE and demarcate and be related to 12, according to the new measurement data of T/C and flux pattern reconstruct state, set up T/C and demarcate relation.
Particularly, in the present invention, EXCORE demarcates the concrete form of relation, according to the difference of subsequent applications and correlation parameter definition and slightly different.The corresponding relation of the Axial power difference AOin that for example in the Axial power difference AOex of EXCORE reading sign and heap, the three-dimensional power of reconstruct distributes, can use (AOin=a*AOex+b) expression.The corresponding relation of power level Pin in the power level Pex being characterized by EXCORE reading and heap can be used expressions such as (Pin=K*Pex) simultaneously.EXCORE calibration coefficient at least comprises the coefficients such as a, b, k.
In the present invention, direct corresponding relation according to the three-dimensional power distribution (being flux pattern reconstruct state) of reconstruct in heap with the reading of ex-core detector, can represent with the T matrix of transmission matrix (NX*NX) and single diagonal matrix S of electric current sensitive matrix (NX*NX) etc.Wherein NX has characterized the axial susceptibility quantity of ex-core detector.
Particularly, in the present invention, the concrete form of the calibration coefficient of T/C is relevant to follow-up application scenarios.The Core cooling agent outlet temperature that for example T/C characterizes and the temperature difference of temperature in, can be used for conversion and solve coolant channel enthalpy liter, and enthalpy liter can be converted to the axial integrated power of T/C location component.Therefore the T/C calibration coefficient under this application scenarios is expressed as (MF=P/H), wherein MF stirs and make muddy the factor also referred to as Mixing Factor or title, P is by the distribute integrated power of the T/C module position that obtains of the three-dimensional power of reconstruct, and H is by the poor enthalpy liter calculating of entrance outlet temperature in T/C coolant channel.
As shown in Figure 2, the method for this continuous monitoring of nuclear reactor constantly power uncertainty analysis comprises:
S201, inscribes at least one parameter of reactor core theoretical parameter is carried out to disturbance at consecutive hours, to construct continuous disturbance state.
The present embodiment starts from the theoretical model state that the consecutive hours of reactor core is inscribed, according to the support of reactor core long-time running experience and a large amount of measurement data, structure is the Disturbance Model of moment theory state relatively continuously, is called continuous disturbance state, the continuous actual reactor core state constantly of representative.
It should be noted that, in the present invention, realize from continuous arranging opinion state to disturbing continuously dynamic process, by repeatedly a large amount of parameter perturbations, realize.Excitation parameter definition is with disturb dynamic excitation parameter in Fig. 1 from flux pattern theory state to flux pattern consistent.But the present invention has significantly different to the perturbation amplitude of disturbing continuously dynamic process from the perturbation amplitude of disturbing dynamic perturbation process to flux pattern from the theoretical state of flux pattern from continuous arranging opinion state.This is to cause because continuous reactor core state constantly in the present invention has higher dirigibility by the reactor core state constantly of measuring than flux pattern.
S202, according to the physical characteristics of continuous disturbance state and measurement hardware, constructs the theoretical measurement data of hardware under continuous disturbance state.
In the present invention, according to the physical characteristics of the hardware such as continuous disturbance state and EXCORE or T/C, construct the theoretical measured value (measured value as theoretical in continuous disturbance EXCORE or the theoretical measured value of T/C) under continuous disturbance reactor core state.
S203, respectively measures the uncertainty of hardware, to produce new measurement data to the theoretical measurement data increase in S202.
Particularly, the uncertain disturbances to hard ware measures such as the theoretical measured value of continuous disturbance EXCORE or the theoretical measured value increase EXCORE of T/C or T/C, forms consecutive hours and inscribes new measured value (measured value as new in EXCORE, the new measured value of T/C).
It should be noted that, in the present invention from continuous disturbance state to corresponding hardware theoretical measured value, to shown in Fig. 1 in the process of new measured value and the present invention from flux pattern disturbance state to corresponding hardware theoretical value, to the process of new measured value, be identical, and should be consistent.
S204, obtains the power of reactor core monitoring constantly continuously according to the new measurement data in S203 and demarcation relation and distributes, and wherein demarcation relation characterizes precision lower but the measurement hardware of continuous coverage and the corresponding relation that flux pattern is measured power distribution results constantly.
In the present invention according to new measured value (measured value as new in EXCORE, the new measured value of T/C), and the demarcation relation (as EXCORE calibration coefficient, T/C calibration coefficient) of hard ware measure value and core power distribution foundation, by the processing of on-line monitoring software systems, the reactor core monitoring power that can obtain the continuous moment distributes, and is called continuous monitoring reactor core state.
It should be noted that, in the present invention, by new measured value, in conjunction with calibration coefficient, in the processing of software processing system, obtain continuously the specific algorithm process of the power distribution in the moment, with the algorithmic procedure of the calibration coefficient of being set up by new measured value and the distribution of flux pattern reconstruct power in Fig. 1, it is inverse process.
It is example that measurement data and the calibration coefficient of EXCORE hardware take in the present invention, for the power parameter in acquisition heap is as AOin, according to the continuous measurement data constantly of EXCORE, obtain the Axial power difference AOex of out-pile, according to calibration coefficient a, b, in conjunction with formula (AOin=a*AOex+b), calculate.
S205, determines according to continuous disturbance state and the distribution of the continuous monitoring of reactor core constantly power the uncertainty that on-line continuous moment reactor core monitoring power distributes.
In the present invention according to continuous monitoring reactor core state and continuously constantly reactor core disturb dynamic comparing calculation analysis, can finally determine that reactor core monitors total uncertainty of power distribution continuously.Determine total probabilistic method of core power distribution constantly continuously and total uncertainty that definite flux pattern core power constantly distributes, be identical in method.
Compared with prior art, method of the present invention has realized the probabilistic analysis of continuous moment reactor core monitoring power, introduce in the method hardware and demarcated analog computation (demarcation relation), realized from flux pattern constantly core power distribute overall uncertainty analysis flow process to the distribute transformation of overall uncertainty analysis flow process of continuous moment reactor core monitoring power, can simulate the many demarcating steps of long time period (in burnup circulation) (as a plurality of flux patterns are demarcated) and more complicated hardware system and (comprise TIP/SPD, EXCORE, TC etc.) observation process, thereby can improve controllability and the security of reactor core operation, discharged thermal technology's allowance, improved power station economy.
In addition, in target unit and target fuel recycle for reactor core Application of Monitoring System in the present invention, repeat theory and the perturbation analysis of a large amount of Fig. 1 and Fig. 2 example, can set up merit rating and the sensitivity analysis of the overall core power distribution monitoring under, various software processing technology uncertain based on various hardware foundations and measurement of correlation.
Invention has been described for above combination most preferred embodiment, but the present invention is not limited to the embodiment of above announcement, and should contain the various modifications of carrying out according to essence of the present invention, equivalent combinations.
Claims (10)
1. a method for flux pattern nuclear reactor monitoring constantly power uncertainty analysis, is characterized in that, comprising:
(1) the theoretical state of theoretical reactor core parametric configuration flux pattern of inscribing while measuring according to reactor core flux pattern;
(2) when described flux pattern is measured, inscribe at least one parameter of described theoretical reactor core parameter is carried out to disturbance, to construct flux pattern disturbance state;
(3) according to the physical characteristics of described flux pattern disturbance state and measurement hardware, the theoretical measurement data of structure hardware;
(4) the described theoretical measurement data in (3) is increased to the uncertainty of measuring hardware described in each, to produce new measurement data, described new measurement data comprises the new measurement data of EXCORE, the new measurement data of T/C, TIP or the new measurement data of SPD;
(5) by the data input processing software under TIP or the new measurement data of SPD and the theoretical state of described flux pattern, obtain flux pattern reconstruct state;
(6) according to described flux pattern disturbance state and flux pattern reconstruct state, determine total uncertainty that described flux pattern measurement reactor core monitoring constantly power distributes.
2. the method for claim 1, is characterized in that, described theoretical reactor core parameter comprises boron CONCENTRATION DISTRIBUTION deviation, control rod rod position step-out deviation, radially power distribution bias, axial power distribution bias, Xenon transient state and burnup profile deviation.
3. the method for claim 1, it is characterized in that, described measurement hardware comprises packaged type detection system (RIC/TIP) in heap, heap internally-fixed detection system (RIC/FID), core temperature measuring system (T/C), out-pile Nuclear measurement system (EXCORE).
4. the method for claim 1, it is characterized in that, the described theoretical measurement data in step (3) comprises the theoretical measurement data of EXCORE ex-core detector, the theoretical measurement data of detector in the theoretical measurement data of T/C thermopair, the interior detector of TIP packaged type heap or the fixed heap of SPD.
5. method as claimed in claim 4, is characterized in that, the theoretical measurement data of constructing described EXCORE ex-core detector specifically comprises:
Under described flux pattern disturbance state, by reactor core Nodal, calculate three-dimensional Flux Distribution φ (i, j, k) in structure heap, and in conjunction with the heap of three-dimensional (or two dimension adds one dimension) interior-out-pile response matrix W (i, j, k, m) calculates.
6. method as claimed in claim 4, is characterized in that, the theoretical measurement data of constructing described T/C thermopair specifically comprises:
Under described flux pattern disturbance state, determine near the power data coolant channel at T/C thermopair place, and the enthalpy that described power data is converted into T/C coolant channel is risen to H
deldata;
According to the coolant inlet temperature T of reactor core name
in, coolant pressure P, by cooling medium physical property, calculate coolant entrance enthalpy H
in;
According to described entrance enthalpy H
inand enthalpy rises H
delobtain exporting enthalpy H
out:
H
out＝H
in+H
del；
According to described coolant pressure P and outlet enthalpy H
outobtain coolant temperature:
T
out=f (H
out, P), wherein f is the physical property function that cooling medium is relevant.
7. method as claimed in claim 4, is characterized in that, the theoretical measurement data of constructing detector in described TIP packaged type heap specifically comprises:
Fission reaction cross-sectional distribution (the ∑ of the physics macroscopic view (or microcosmic) of the calculative determination TIP probe by Nodal method under described flux pattern disturbance state
f1and ∑
f2), and the Flux Distribution (φ of definite TIP probe positions
1and φ
2), by calculating the fission reaction rate RR of TIP, obtain, wherein RR=φ
1* ∑
f1+ φ
2* ∑
f2.
8. a method for the continuous monitoring of nuclear reactor constantly power uncertainty analysis, is characterized in that, comprising:
(1) at consecutive hours, inscribe at least one parameter of reactor core theoretical parameter is carried out to disturbance, to construct continuous disturbance state;
(2), according to the physical characteristics of described continuous disturbance state and measurement hardware, construct the theoretical measurement data of hardware under described continuous disturbance state;
(3) the described theoretical measurement data in (2) is increased to the uncertainty of measuring hardware described in each, to produce new measurement data;
(4) according to the described new measurement data in (3) and demarcation relation, obtain the power of reactor core monitoring constantly continuously and distribute, wherein said demarcation relation characterizes precision lower but the described measurement hardware of continuous coverage and the corresponding relation that flux pattern is measured power distribution results constantly;
(5) according to described continuous disturbance state and the distribution of described continuous moment reactor core monitoring power, determine the uncertainty that on-line continuous reactor core monitoring constantly power distributes.
9. method as claimed in claim 8, is characterized in that, inscribes produced new measurement data and flux pattern reconstruct state is determined described demarcation relation during according to flux pattern.
10. method as claimed in claim 9, is characterized in that, inscribes the detailed process of new measurement data and the generation of flux pattern reconstruct state during described flux pattern as described in claim 1-7 any one.
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