CN104036837B - Flux pattern moment and continuously moment reactor core monitoring power uncertainty analysis method - Google Patents
Flux pattern moment and continuously moment reactor core monitoring power uncertainty analysis method Download PDFInfo
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Abstract
The method that the invention discloses the monitoring power uncertainty analysis of a kind of flux pattern moment nuclear reactor, including structure flux pattern theory state；Structure flux pattern disturbance state；The theoretical measurement data of structure hardware；Increase and measure the uncertainty of hardware to produce new measurement data；Obtain flux pattern reconstruct state；Reconstruct state according to flux pattern disturbance state and flux pattern and determine that flux pattern measures the total uncertain of moment reactor core monitoring power distribution.Compared with prior art, the method is when determining overall uncertain amount, need not consider item by item, analyze each uncertain component, the error of this overall uncertain amount is decreased in the case of the relative independentability of each uncertain component weakens, reliability and engineer applied for reactor core monitoring system provide the foundation, improve controllability and safety that reactor core runs, release thermal technology's allowance, improve power station economy.The method that the present invention discloses the monitoring power uncertainty analysis of a kind of continuous moment nuclear reactor.
Description
Technical field
The present invention relates to nuclear reactor power distribution technology field, when relating more specifically to a kind of flux pattern
Carve and moment nuclear reactor monitors power Uncertainty Analysis Method continuously.
Background technology
Generally, need periodically to monitor reactor core in nuclear reactor running (or real-time online)
Interior three-dimensional power distribution, analyzes the uncertainty of core power distribution, to verify the operation controllability of reactor core
And safety.
Refer to document " US-APWR Incore Power Distribution Evaluation Methodology.
MUAP-07021-NP (R0) (Non-Proprietary Version), December2007 ", about core power
The uncertainty analysis of distribution, according to the physical process of flux pattern In-core Instrumentation, power is distributed overall the most not
Definitiveness is divided into following component:
Wherein:
Represent the uncertainty of local rod power distribution
Represent that measuring activity is converted to measure the uncertainty that the process of power introduces
Represent that measuring power derives, from measuring point, the uncertainty that non-measured point is introduced
Characterize the uncertainty of measurement data itself
According to the concrete meaning of each component, it is analyzed item by item.WhereinDepend on the theoretical pre-ranging of reactor core
The precision of the excellent power reconstructed module of sequence (such as reactor core locking nub method program),Depend on theoretical prediction program from
Measure activity and be converted to measure the precision of the conversion coefficient of power.
AndThen need, according to on-the-spot actual physics measurement data, to analyse item by item, then carry out total
Body is probabilistic to be determined.
In said method, component involved in the uncertainty analysis of core power distribution (is included the most true
Qualitative component) consider item by item, analyze so that error is relatively big, thus is difficult for heap
Reliability and the engineer applied of core monitoring system provide basis.
It addition, in order to improve controllability and the safety that reactor core runs, in addition it is also necessary to continuous moment reactor core is monitored
The uncertainty of power distribution is analyzed.
Summary of the invention
It is an object of the invention to provide a kind of flux pattern moment nuclear reactor monitoring power uncertainty analysis
Method, the method is when determining overall uncertain amount, it is not necessary to considers item by item, analyze each uncertainty
Component, reduces this overall uncertain amount with the relative independentability at each uncertain component in the case of weakening
Error, provide basis for the reactor core monitoring reliability of system and engineer applied, that improves that reactor core runs is controlled
Property and safety.
It is a further object of the present invention to provide a kind of power uncertainty of moment nuclear reactor monitoring continuously to divide
The method of analysis, to improve controllability and the safety that reactor core runs.
For achieving the above object, the invention provides a kind of flux pattern moment nuclear reactor monitoring power not
The method of deterministic parsing, including:
(1) the theoretical reactor core parametric configuration flux pattern theory state inscribed when measuring according to reactor core flux pattern；
(2) inscribe at least one parameter to theoretical reactor core parameter when flux pattern is measured and carry out disturbance, with structure
Make flux pattern disturbance state；
(3) according to flux pattern disturbance state and the physical characteristic of measurement hardware, the theoretical measurement data of structure hardware；
(4) the theoretical measurement data in (3) is increased the uncertainty of each measurement hardware, to produce new survey
Amount data, new measurement data includes the new measurement data of EXCORE, the new measurement data of T/C, TIP or SPD
New measurement data；
(5) by the data input processing software under new for TIP or SPD measurement data and flux pattern theory state,
State is reconstructed to flux pattern；
(6) reconstruct state according to flux pattern disturbance state and flux pattern and determine that flux pattern measures moment reactor core monitoring power
Total uncertainty of distribution.
Compared with prior art, the method for the present invention is from structure flux pattern theory state, in the flux pattern moment
Theoretical reactor core parameter is carried out error disturbance to construct flux pattern disturbance state, in the case of there is no measurement data,
According to operating experience and the physical principle characteristic of each measurement hardware, construct the theoretical measurement data of hardware, and
Measure the uncertainty of hardware by theoretical measurement data superposition and (i.e. simulate reality to produce new measurement data
Border measurement data), obtain flux pattern reconstruct state, last root further according to flux pattern theory state and new measurement data
The uncertainty of flux pattern moment reactor core monitoring power distribution is determined according to flux pattern disturbance state and reconstruct state；That is,
The method is when determining overall uncertain amount, it is not necessary to considers item by item, analyze each uncertain component,
The relative independentability of each uncertain component decreases the error of this overall uncertain amount in the case of weakening,
Provide the foundation for the reactor core monitoring reliability of system and engineer applied, improve controllability that reactor core runs and
Safety, releases thermal technology's allowance, improves power station economy.
Specifically, theoretical reactor core parameter includes boron concentration distribution bias, controls stick position step-out deviation, radially
Power distribution bias, axial power distribution bias, Xenon transient state and burnup profile deviation.
Specifically, measure hardware and include packaged type detection system (RIC/TIP), the spy of heap internally-fixed in heap
Examining system (RIC/FID), core temperature measure system (T/C), out-pile Nuclear measurement system (EXCORE).
Specifically, the theoretical measurement data in step (3) includes the theoretical survey of EXCORE ex-core detector
In amount data, the theoretical measurement data of T/C thermocouple, TIP packaged type heap, detector or SPD are fixed
The theoretical measurement data of detector in heap.
Specifically, the theoretical measurement data of structure EXCORE ex-core detector specifically includes:
Flux Distribution three-dimensional in calculating structure heap by reactor core Nodal under flux pattern disturbance state
φ (i, j, k), and combine in the heap of three-dimensional (or two dimension adds one-dimensional)-(i, j, k m) are calculated out-pile response matrix W.
Specifically, the theoretical measurement data of structure T/C thermocouple specifically includes:
The power data near the coolant channel at T/C thermocouple place is determined under flux pattern disturbance state, and
The enthalpy that power data is converted into T/C coolant channel rises HdelData；
Coolant inlet temperature T according to reactor core namein, coolant pressure P, by the meter of coolant physical property
Calculation obtains coolant entrance enthalpy Hin；
According to entrance enthalpy HinAnd enthalpy rises HdelObtain exporting enthalpy Hout:
Hout=Hin+Hdel；
According to coolant pressure P and outlet enthalpy HoutObtain coolant temperature:
Tout=f (Hout, P), wherein f is the physical property function that coolant is relevant.
Specifically, in structure TIP packaged type heap, the theoretical measurement data of detector specifically includes:
Under flux pattern disturbance state by the calculating of Nodal method determine physics macroscopic view that TIP pops one's head in (or
Microcosmic) fission reaction cross-sectional distribution (∑f1And ∑f2), and determine the Flux Distribution (φ of TIP probe positions1
And φ2), obtain by calculating the fission reaction rate RR of TIP, wherein RR=φ1×∑f1+φ2×∑f2。
Correspondingly, present invention also offers a kind of power uncertainty of moment nuclear reactor monitoring continuously to divide
The method of analysis, including:
(1) inscribe at least one parameter to reactor core theoretical parameter at consecutive hours and carry out disturbance, with structure continuously
Disturbance state；
(2) according to continuous disturbance state and the physical characteristic of measurement hardware, the reason of hardware under continuous disturbance state is constructed
Opinion measurement data；
(3) the theoretical measurement data in (2) is increased the uncertainty of each measurement hardware, to produce new survey
Amount data；
(4) continuous moment reactor core monitoring power is obtained according to the new measurement data in (3) and demarcation relation
Distribution, relation of wherein demarcating characterizes that precision is relatively low but that measure continuously measurement hardware measures merit with the flux pattern moment
The corresponding relation of rate distribution results；
(5) monitor power distribution according to continuous disturbance state and continuous moment reactor core and determine on-line continuous moment reactor core
The uncertainty of monitoring power distribution.
Compared with prior art, The inventive method achieves continuous moment reactor core monitoring power uncertainty
Analysis, introduce in the method hardware demarcate simulation calculate (demarcation relation), it is achieved that when flux pattern
Carve the core power overall uncertainty analysis flow process of distribution the most true to the monitoring power distribution of continuous moment reactor core
The transformation of qualitative analysis flow process, can simulate long time period (in combustion cycle) many demarcating steps (as many
Individual flux pattern is demarcated) and the prison of more complicated hardware system (including TIP/SPD, EXCORE, TC etc.)
Survey process, such that it is able to improve controllability and the safety that reactor core runs, releases thermal technology's allowance, improves electricity
Stand economy.
Specifically, according to flux pattern inscribe produced new measurement data time and flux pattern reconstruct state determines demarcation
Relation.
Specifically, new measurement data and the detailed process as above institute of flux pattern reconstruct state generation are inscribed during flux pattern
State.
By description below and combine accompanying drawing, the present invention will become more fully apparent, and these accompanying drawings are used for explaining
Embodiments of the invention.
Accompanying drawing explanation
Fig. 1 is the stream of the method for flux pattern moment nuclear reactor of the present invention monitoring power uncertainty analysis
Cheng Tu.
Fig. 2 is the flow process of the method for the present invention nuclear reactor of continuous moment monitoring power uncertainty analysis
Figure.
Detailed description of the invention
With reference now to accompanying drawing, describing embodiments of the invention, element numbers similar in accompanying drawing represents similar unit
Part.
The invention belongs to the nuclear power station reactor core monitoring system regions of 30～2,000,000 kilowatts of (electrical power) ranks,
Be suitable for include the most secondary add nuclear power station LOCA nargin monitoring system (LSS), three generations add nuclear power station (as
AP1000 and EPR) reactor core three-dimensional on-line monitoring system (OMS) etc..
Refer to Fig. 1, the method for flux pattern moment nuclear reactor of the present invention monitoring power uncertainty analysis
Specifically include that
S101, the theoretical reactor core parametric configuration flux pattern theory state inscribed when measuring according to reactor core flux pattern.
S102, inscribes at least one parameter to theoretical reactor core parameter and carries out disturbance when flux pattern is measured, with
Structure flux pattern disturbance state.
In new operation reactor and instrument, owing to lacking operating measurement data, therefore can be by with reference to instrument
The measured data of table obtains the difference of actual reactor core and Design Theory reactor core.Setting-out such as current domestic main flow
The measurement result of heap RIC system, can be used for the difference defining actual reactor core with theoretical reactor core.Therefore, this
The bright actual reactor core determined according to reference meter under flux pattern and the deviation of theoretical reactor core, construct disturbance reactor core generation
The actual reactor core of table.
Specifically, the present invention is when defining the difference of actual reactor core and theoretical reactor core, available to theoretical reactor core ginseng
At least one parameter of number carries out disturbance, represents actual reactor core constructing disturbance reactor core, i.e. realizes reactor core reality
The simulation of border state.Wherein, disturbance parameter can be current reactor core state representation amount, such as boron concentration (boracic
Presurized water reactor), boron concentration distribution bias, the stick position step-out deviation of controlling, or join for the change of power distribution shape
Number (such as radial direction power distribution bias, axial power distribution bias, Xenon transient state), it is also possible to fire for reactor core
Consumption history run parameter (such as burnup profile deviation, nucleon distribution density).
It practice, the present embodiment starts from the flux pattern theoretical model state of reactor core, long-term according to flux pattern
Service data and the support of experience, construct the Disturbance Model corresponding to theory state, referred to as flux pattern disturbance state.
Flux pattern longtime running data include the measured value of the real power distribution of substantial amounts of actual reactor core, should
Measured value and the deviation of the value of calculation of reactor core Design Theory, characterize the distribution of actual core power and design reactor core
The difference degree of power distribution.The power distribution bias of measured value Yu design load is carried out statistical analysis by the present invention,
And determine power distribution bias source and inclined extent.The running technology specification and in theory run from reactor core
The influence factor that can affect reactor core operation sets out, and the deviation that power is distributed is converted to a series of reactor core by the present invention
The parameter perturbation of parameter characterization, and determine parameter perturbation amplitude.Specifically, by the merit measured with Design Theory
The deviation of rate distribution is converted to the deviation of reactor core parameter perturbation, generally by the actual fortune of a large amount of operating experiences and power plant
The restrictive condition of row, obtains through evaluation calculation.And parameter perturbation amplitude, with the experimental data of actual motion
Based on storehouse, obtain through evaluation calculation.
S103, according to flux pattern disturbance state and the physical characteristic of measurement hardware, the theoretical of structure hardware measures number
According to.Wherein, measure hardware and include packaged type detection system (RIC/TIP), the detection of heap internally-fixed in heap
System (RIC/FID), core temperature measure system (T/C), out-pile Nuclear measurement system (EXCORE).
From flux pattern disturbance state in the present invention, construct the theoretical measurement data of each reactor core hardware condition, bag
Include the theoretical measurement data of EXCORE ex-core detector, the theoretical measurement data of T/C thermocouple, TIP can
The theoretical measurement data of detector in detector or the fixed heap of SPD in portable heap.Specifically, this
The calculating of bright middle theoretical measurement data, puts into reactor core state during reactor core and the thing of hardware itself according to hardware
Reason characteristic principle obtains.
Specifically, the detailed process of structural theory measurement data is as follows:
(1) the theoretical measurement data of EXCORE ex-core detector
According to physical characteristic, the reading of EXCORE derive from fine power three-dimensional in heap or flux (as
Fast group flux φ (i, j, k), the coordinate of the specifiable lattice in i, j, k corresponding three-dimensional space.Typically in x-y plane in heap
On be divided into NX*NY grid, be divided into NZ grid in z-direction), through Neutron Transport Theory, arrive heap
The flux of external detector position can react with the material of EXCORE, and produces electric current.In heap, neutron leads to
Measure and arrive ex-core detector through Neutron Transport Theory and produce the process of electric current, the widely used screen of industry can be passed through
Cover or Monte Carlo Calculation software (such as MCNP) etc. is simulated, and be calculated in heap three-dimensional power (or
Flux) with the corresponding relation of ex-core detector, referred to as in heap out-pile response matrix W (i, j, k, m), wherein i, j, k
For the coordinate of grid a certain in three dimensions in heap, m then for some concrete ex-core detector (or
Detector sensitive segment).
Therefore in the present invention, the theoretical measurement data of EXCORE ex-core detector, it is expressed as CprdM (), can
From reactor core flux pattern disturbance state, by reactor core Nodal calculate (as commercial ANC, SMART,
The locking nub programs such as SIMULATE) in structure heap three-dimensional flux (or power) distribution phi (i, j k), and tie
In the heap of conjunction three-dimensional (or two dimension adds one-dimensional)-(i, j, k, m) by being calculated for out-pile response matrix W.
(2) the theoretical measurement data of T/C thermocouple
According to physical characteristic, the reading of T/C thermocouple characterizes the reactor coolant of core exit T/C position
Temperature, and coolant outlet temperature, with the inlet temperature of coolant channel and the heating in this passage
The enthalpy of the coolant caused rises relevant.The enthalpy of coolant rises simultaneously with the power of the fuel near coolant channel
The most proportional.
Therefore in the present invention, the theoretical measurement data of T/C thermocouple, can from reactor core flux pattern disturbance state,
Determine the power data near the coolant channel at T/C thermocouple place, be converted into T/C coolant channel
Enthalpy rises HdelData.Coolant inlet temperature T according to reactor core name (specified)in, coolant pressure P, can
It is calculated coolant entrance enthalpy H by coolant physical propertyin.The physical property table of coolant, refers to coolant
Temperature, pressure, enthalpy, vaporize, the corresponding relation table of liquefaction etc.).According to entrance enthalpy and enthalpy liter, can calculate
Obtain exporting enthalpy.
Hout=Hin+Hdel
Enthalpy H at setting pressure P and coolantout, it is calculated coolant temperature.
Tout=f (Hout,P)
Wherein f is the physical property function that coolant is relevant.
(3) the theoretical measurement data of detector in TIP packaged type heap
According to physical characteristic, the flux of TIP position in the reading of detector derives from heap in TIP packaged type heap
(include fast group φ1And hot group φ2) with TIP probe sensitive species (such as U235) occur fission reaction also
And then generation current indication.This current indication is directly proportional to the fission reaction rate of TIP position, and fission reaction
Rate (includes fast group's fission cross section ∑ with the fission reaction cross section of the material of TIP probef1And hot group's fission cross section
∑f2) and the flux level (φ of TIP probe positions1And φ2) relevant.
Therefore in the present invention, the theoretical measurement data of TIP packaged type detector, can be from reactor core flux pattern disturbance
Set out, by the calculating of Nodal method (such as commercial ANC, SMART, SIMULATE constant pitch
Block program) determine the fission reaction cross-sectional distribution (∑ of physics macroscopic view (or microcosmic) that TIP pops one's head inf1And ∑f2),
And determine the Flux Distribution (φ of TIP probe positions1And φ2), obtain by calculating the fission reaction rate RR of TIP
Arrive.
RR=φ1×∑f1+φ2×∑f2
(4) the theoretical measurement data of detector in the fixed heap of SPD
According to physical characteristic, in the fixed heap of SPD, detector measures current source SPD position in heap
Flux and the absorption response effect of SPD probe sensitivity, the electronics sent arrives the absorption of SPD and produces the most afterwards
Electric current.
Therefore, in the present invention, the theoretical measurement data of SPD stationary detector produces process, can move with TIP
The theoretical measurement data of dynamic formula detector is similar, but occurs the response type of electric current and mechanism slightly different.
S104, increases the uncertainty of each measurement hardware to the theoretical measurement data in S103, to produce new survey
Amount data.
Any reactor core hard ware measure all can have the uncertainty of measurement.In the present invention, theoretical for EXCORE
Measurement data, T/C theory measurement data, TIP or SPD theory measurement data, increase each measurement hardware not
Definitiveness, produces new measurement data respectively, measurement data as new in EXCORE, the new measurement data of T/C,
The new measurement data of TIP or SPD.It should be noted that the precision of different hardware systems and uncertainty
Difference is higher than T/C measures power accuracy as the precision that TIP measures power.
Specifically, by theoretical measurement data C in the present inventionprdTo new measurement data CmesProcess, by giving
The introducing of the fixed different measuring probabilistic random error relevant to different hardware realizes.
Cmes=Cprd×(1+δ)
Measuring uncertainty characterizes measured value random under 95%-95% confidence level under obeying the most too distribution
Situation of change.Therefore in the present invention, δ according to the concept of measuring uncertainty, meter by the way of stochastic sampling
Obtain.For different hard ware measure uncertainties and the difference of the time of stochastic sampling, δ is different.
For embodying the most too Distribution Effect of δ sampling, the present invention is repeated this simulation process in a large number.
S105, by the data input processing software under new for TIP or SPD measurement data and flux pattern theory state,
Obtain flux pattern reconstruct state.
The hardware of TIP and SPD represents In-core Instrumentation high-precision measurement hardware at present.Leading in the present invention
In spirogram software processes, with high-precision hard ware measure data (such as TIP or SPD measurement data) with
And the data under corresponding reactor core flux pattern theory state input as software, can obtain with the reconstruct of output flow figure
Three-dimensional power distribution.The three-dimensional power distribution that this reconstruct is obtained, referred to as flux pattern reconstruct state.
It should be noted that in the present invention, the detector characterized due to the new measurement data of TIP or SPD anti-
Should the current indication that causes of rate (include fission or absorb reaction), need passing flux figure software to measure new
Data process.Flux pattern processes in software, utilizes power that flux pattern theory state provides and response rate
Ratio, is converted to the power data measured by measurement data.Owing to TIP or SPD measurement data only covers
The measured zone that reactor core is few, processes software hence with flux pattern, the merit provided in conjunction with flux pattern theory state
Rate is distributed, the power data that will measure, and expands into the power distribution that full heap is three-dimensional, is referred to as the three-dimensional merit of reconstruct
Rate is distributed, i.e. the reconstruct of flux pattern in present invention state.
S106, reconstructs state according to flux pattern disturbance state and flux pattern and determines that flux pattern measures moment reactor core monitoring merit
Total uncertainty of rate distribution.
In the present invention, the core power distribution according to flux pattern reconstruct state is relative to representing the logical of reactor core virtual condition
Spirogram disturbs the change between the distribution of dynamic core power, and computational analysis obtains flux pattern monitoring core power and divides
Total uncertainty of cloth.
Owing to the power distribution of reconstruct state is the normalized distribution of reactor core with disturbing the distribution of dynamic power.By heap
The reactor core deviation profile that two normalized distributions of core determine, from the angle of probability statistics, is just obeying standard
It is distributed very much, is therefore distributed the most very much the 95%-95% confidence interval determined by this and is flux pattern monitoring core power
Total uncertainty of distribution.
Compared with prior art, the method for the present invention is from structure flux pattern theory state, in the flux pattern moment
Theoretical reactor core parameter is carried out error disturbance to construct flux pattern disturbance state, in the case of there is no measurement data,
According to operating experience and the physical principle characteristic of each measurement hardware, construct the theoretical measurement data of hardware, and
Measure the uncertainty of hardware by theoretical measurement data superposition and (i.e. simulate reality to produce new measurement data
Border measurement data), obtain flux pattern reconstruct state, last root further according to flux pattern theory state and new measurement data
The uncertainty of flux pattern moment reactor core monitoring power distribution is determined according to flux pattern disturbance state and reconstruct state；That is,
The method is when determining overall uncertain amount, it is not necessary to considers item by item, analyze each uncertain component,
The relative independentability of each uncertain component decreases the error of this overall uncertain amount in the case of weakening,
Provide the foundation for the reactor core monitoring reliability of system and engineer applied, improve controllability that reactor core runs and
Safety, releases thermal technology's allowance, improves power station economy.
Refer to Fig. 2 again, present invention also offers a kind of monitoring power of moment nuclear reactor continuously uncertain
Property analyze method.
It should be noted that in the present invention due to higher precision measurement hardware system (such as TIP system) no
Can be the most real-time carry out reactor core monitoring, it is therefore desirable to reactor core precision relatively low but measure continuously support hardware (as
EXCORE and T/C) provide the measurement data of reactor core on-line continuous monitoring to originate.The present invention is according to flux pattern
The reconstruction calculations of software, be respectively directed to monitor continuously each measure hardware set up with higher precision but discontinuous
The relation of three-dimensional power that hard ware measure is reconstructed distribution, sets up process for this corresponding relation, is referred to as mark
Devise a stratagem is calculated.In the present invention, reconstruct state according to the new measurement data of the EXCORE in Fig. 1 and flux pattern and set up
EXCORE demarcates relation 12, reconstructs state according to the new measurement data of T/C and flux pattern and sets up T/C demarcation relation.
Specifically, in the present invention, EXCORE demarcates the concrete form of relation, according to subsequent applications and relevant
Parameter definition difference and slightly different.Such as EXCORE reading characterize Axial power difference AOex with
The corresponding relation of the Axial power difference AOin of the three-dimensional power distribution of reconstruct in heap, Ke Yiyong
(AOin=a*AOex+b) represent.In the power level Pex simultaneously characterized by EXCORE reading and heap
The corresponding relation of power level Pin can represent with (Pin=K*Pex) etc..Then EXCORE calibration coefficient
The most at least include the coefficients such as a, b, k.
In the present invention, detect with out-pile according to three-dimensional power distribution (i.e. flux pattern reconstruct state) of reconstruct in heap
The direct corresponding relation of the reading of device, can use T matrix and the current sense square of transmission matrix (NX*NX)
Single diagonal matrix S expression etc. of battle array (NX*NX).Wherein NX characterizes the axial sensitive of ex-core detector
Number of degrees amount.
Specifically, in the present invention, the concrete form of the calibration coefficient of T/C is relevant to follow-up application scenarios.Example
The Core cooling agent outlet temperature characterized such as T/C and the temperature difference of inlet temperature, can be used for conversion and solve coolant
Channel specific-enthalpy rise, and enthalpy liter can be converted to the axial integrated power of T/C location component.Therefore in this applied field
T/C calibration coefficient under scape is expressed as (MF=P/H), and wherein MF also referred to as Mixing Factor or title stir
The muddy factor, the integrated power of the T/C module position that P is obtained by the three-dimensional power distribution reconstructed, and H is by T/C
Inlet port temperature difference calculated enthalpy liter in coolant channel.
As in figure 2 it is shown, the method for this continuous moment nuclear reactor monitoring power uncertainty analysis includes:
S201, inscribes at least one parameter to reactor core theoretical parameter at consecutive hours and carries out disturbance, with the company of structure
Continuous disturbance state.
The present embodiment starts from the theoretical model state that the consecutive hours of reactor core is inscribed, according to reactor core longtime running warp
Test and the support of big amount measurement data, the Disturbance Model of structure moment theory state relatively continuously, be referred to as continuously
Disturbance state, represents the true reactor wick-like state in continuous moment.
It should be noted that the present invention realizes from continuous arranging opinion state to disturbing dynamic process continuously, by many
Secondary substantial amounts of parameter perturbation realizes.From flux pattern theory state to flux pattern disturbance in disturbance parameter definition and Fig. 1
The disturbance parameter of state is consistent.But, present invention disturbance width during continuous arranging opinion state to continuous disturbance state
Degree has the most different from the perturbation amplitude disturbing dynamic perturbation process from flux pattern theory state to flux pattern.
This is owing to the reactor core state measuring the moment than flux pattern is had more by the reactor core state in moment continuous in the present invention
High motility causes.
S202, according to continuous disturbance state and the physical characteristic of measurement hardware, constructs hardware under continuous disturbance state
Theoretical measurement data.
Physical characteristic according to hardware such as continuous disturbance state and EXCORE or T/C in the present invention, structure is even
Theoretical measured value under continuous disturbance reactor core state is (as theoretical in continuous disturbance EXCORE theory measured value or T/C
Measured value).
S203, increases the uncertainty of each measurement hardware to the theoretical measurement data in S202, to produce new survey
Amount data.
Specifically, continuous disturbance EXCORE theory measured value or T/C theory measured value are increased EXCORE
Or the uncertain disturbances of the hard ware measure such as T/C, form consecutive hours and inscribe new measured value (such as EXCORE
New measured value, the new measured value of T/C).
It should be noted that from continuous disturbance state to corresponding hardware theory measured value in the present invention, to new
The process of measured value with shown in Fig. 1 in the present invention from flux pattern disturbance state to corresponding hardware theoretical value, arrive
The process of new measured value is identical, and should keep consistent.
S204, obtains continuous moment reactor core monitoring power according to the new measurement data in S203 and demarcation relation
Distribution, relation of wherein demarcating characterizes that precision is relatively low but that measure continuously measurement hardware measures merit with the flux pattern moment
The corresponding relation of rate distribution results.
According to new measured value (measured value as new in EXCORE, the new measured value of T/C) in the present invention, and firmly
The demarcation relation that part measured value and core power distribution are set up is (as EXCORE calibration coefficient, T/C demarcate system
Number), by the process of online-monitoring software system, it is possible to obtain the reactor core monitoring power distribution in moment continuously,
It is referred to as monitoring reactor core state continuously.
It should be noted that in the present invention, new measured value combine calibration coefficient, at software processing system
Process obtain the continuous moment power distribution specific algorithm process, with Fig. 1 in by new measured value and flux pattern
The algorithmic procedure of the calibration coefficient that reconstruct power distribution is set up, is inverse process.
The present invention is as a example by the measurement data and calibration coefficient of EXCORE hardware, for obtaining the power ginseng in heap
Number such as AOin, according to the measurement data in EXCORE continuous moment, obtains the Axial power difference of out-pile
AOex, according to calibration coefficient a, b, is calculated in conjunction with formula (AOin=a*AOex+b).
S205, monitors power distribution according to continuous disturbance state and continuous moment reactor core and determines on-line continuous moment heap
The uncertainty of core monitoring power distribution.
The present invention disturbs dynamic comparing calculation divide according to monitoring reactor core state continuously and continuous moment reactor core
Analysis, can finally determine that reactor core monitors the total uncertain of power distribution continuously.Determine continuous moment core power
It is total uncertain that total probabilistic method of distribution and the core power determining the flux pattern moment are distributed,
It is identical in method.
Compared with prior art, The inventive method achieves continuous moment reactor core monitoring power uncertainty
Analysis, introduce in the method hardware demarcate simulation calculate (demarcation relation), it is achieved that when flux pattern
Carve the core power overall uncertainty analysis flow process of distribution the most true to the monitoring power distribution of continuous moment reactor core
The transformation of qualitative analysis flow process, can simulate long time period (in combustion cycle) many demarcating steps (as many
Individual flux pattern is demarcated) and the prison of more complicated hardware system (including TIP/SPD, EXCORE, TC etc.)
Survey process, such that it is able to improve controllability and the safety that reactor core runs, releases thermal technology's allowance, improves electricity
Stand economy.
It addition, target unit and desired fuel circulation for reactor core Application of Monitoring System are interior in the present invention, weight
The theory of multiple a large amount of Fig. 1 and Fig. 2 examples and perturbation analysis, can set up based on various hardware foundations and correlative measurement
Measure merit rating and the sensitivity of overall core power distribution monitoring under software processing technology uncertain, various
Property analyze.
Above in association with most preferred embodiment, invention has been described, but the invention is not limited in disclosed above
Embodiment, and amendment, the equivalent combinations that the various essence according to the present invention is carried out should be contained.
Claims (10)
1. a method for flux pattern moment nuclear reactor monitoring power uncertainty analysis, its feature exists
In, including:
(1) the theoretical reactor core parametric configuration flux pattern theory state inscribed when measuring according to reactor core flux pattern；
(2) inscribe at least one parameter to described theoretical reactor core parameter when described flux pattern is measured to disturb
Dynamic, to construct flux pattern disturbance state；
(3) according to described flux pattern disturbance state and the physical characteristic of measurement hardware, the theoretical measurement of structure hardware
Data；
(4) the described theoretical measurement data in (3) is increased the uncertainty of each described measurement hardware, with
Produce new measurement data, described new measurement data include the new measurement data of EXCORE, the new measurement data of T/C,
The new measurement data of TIP or SPD；
(5) by the data input processing software under new for TIP or SPD measurement data and described flux pattern theory state,
Obtain flux pattern reconstruct state；
(6) reconstruct state according to described flux pattern disturbance state and flux pattern and determine that described flux pattern measures moment reactor core
Total uncertainty of monitoring power distribution.
2. the method for claim 1, it is characterised in that described theoretical reactor core parameter includes that boron concentration is divided
Cloth deviation, control stick 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 characterised in that described measurement hardware includes packaged type in heap
Detection system (RIC/TIP), heap internally-fixed detection system (RIC/FID), core temperature measurement system (T/C),
Out-pile Nuclear measurement system (EXCORE).
4. the method for claim 1, it is characterised in that the described theoretical measurement number in step (3)
According to including the theoretical measurement data of EXCORE ex-core detector, the theoretical measurement data of T/C thermocouple, TIP
The theoretical measurement data of detector in detector or the fixed heap of SPD in packaged type heap.
5. method as claimed in claim 4, it is characterised in that construct described EXCORE ex-core detector
Theoretical measurement data specifically include:
Flux Distribution three-dimensional in calculating structure heap by reactor core Nodal under described flux pattern disturbance state
φ (i, j, k), and combine three-dimensional or two dimension add in one-dimensional heap-(i, j, k m) are calculated out-pile response matrix W.
6. method as claimed in claim 4, it is characterised in that construct the theoretical measurement of described T/C thermocouple
Data specifically include:
The power data near the coolant channel at T/C thermocouple place is determined under described flux pattern disturbance state,
And the enthalpy that described power data is converted into T/C coolant channel rises HdelData；
Coolant inlet temperature T according to reactor core namein, coolant pressure P, by the calculating of coolant physical property
Obtain coolant entrance enthalpy Hin；
According to described entrance enthalpy HinAnd enthalpy rises HdelObtain exporting enthalpy HouT:
Hout=Hin+Hdel；
According to described coolant pressure P and outlet enthalpy HoutObtain coolant temperature:
Tout=f (Hout, P), wherein f is the physical property function that coolant is relevant.
7. method as claimed in claim 4, it is characterised in that construct detection in described TIP packaged type heap
The theoretical measurement data of device specifically includes:
Determine, by the calculating of Nodal method, the physics macroscopic view that TIP pops one's head under described flux pattern disturbance state
Or the fission reaction cross-sectional distribution ∑ of microcosmicf1And ∑f2, and determine Flux Distribution φ of TIP probe positions1With
φ2, obtain by calculating the fission reaction rate RR of TIP, wherein RR=φ1×∑f1+φ2×∑f2。
8. the method for a continuous moment nuclear reactor monitoring power uncertainty analysis, it is characterised in that
Including:
(1) inscribe at least one parameter to reactor core theoretical parameter at consecutive hours and carry out disturbance, with structure continuously
Disturbance state；
(2) according to described continuous disturbance state and the physical characteristic of measurement hardware, construct under described continuous disturbance state
The theoretical measurement data of hardware；
(3) the described theoretical measurement data in (2) is increased the uncertainty of each described measurement hardware, with
Produce new measurement data；
(4) monitoring of continuous moment reactor core is obtained according to the described new measurement data in (3) and demarcation relation
Power is distributed, and wherein said demarcation relation characterizes that precision is relatively low but that measure continuously described measurement hardware and flux
The figure moment measures the corresponding relation of power distribution results；
(5) monitor power distribution according to described continuous disturbance state and described continuous moment reactor core and determine on-line continuous
The uncertainty of moment reactor core monitoring power distribution.
9. method as claimed in claim 8, it is characterised in that inscribe produced new survey during according to flux pattern
Amount data and flux pattern reconstruct state determine described demarcation relation.
10. method as claimed in claim 9, it is characterised in that inscribe new measurement data during described flux pattern
The detailed process of state generation is reconstructed as described in any one of claim 1-7 with flux pattern.
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| CN105448362B (en) * | 2015-11-23 | 2017-06-30 | 中核核电运行管理有限公司 | By the use of power range detector and signal rod method is carved as the dynamic of signal source |
| CN105373667B (en) * | 2015-11-27 | 2016-08-24 | 西安交通大学 | The multigroup cross section perturbation motion method of uncertainty analysis is calculated for reactor physics |
| CN108074652B (en) * | 2016-11-09 | 2019-09-03 | 国家电投集团科学技术研究院有限公司 | Reactor surveillance and method for early warning and system |
| CN108447574B (en) * | 2018-03-28 | 2020-08-11 | 中广核工程有限公司 | Method and system for calculating neutron counting rate of out-of-reactor detector of nuclear power station |
| CN112509716B (en) * | 2020-11-24 | 2023-11-10 | 华南理工大学 | Method for monitoring three-dimensional power probability distribution of reactor based on information fusion theory |
| CN113643833A (en) * | 2021-07-16 | 2021-11-12 | 广东核电合营有限公司 | Method and device for correcting flux map data of nuclear power station pressurized water reactor and terminal equipment |
| WO2023151786A1 (en) | 2022-02-09 | 2023-08-17 | Framatome Gmbh | Method for controlling a pressurized water reactor, computer program product and control system |
| CN115862912B (en) * | 2023-02-27 | 2023-05-02 | 西安交通大学 | Method for measuring power distribution of pressurized water reactor core under dynamic xenon condition |
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