CN111400869A - Reactor core neutron flux space-time evolution prediction method, device, medium and equipment - Google Patents

Reactor core neutron flux space-time evolution prediction method, device, medium and equipment Download PDF

Info

Publication number
CN111400869A
CN111400869A CN202010115365.4A CN202010115365A CN111400869A CN 111400869 A CN111400869 A CN 111400869A CN 202010115365 A CN202010115365 A CN 202010115365A CN 111400869 A CN111400869 A CN 111400869A
Authority
CN
China
Prior art keywords
neutron flux
reactor core
time
expansion coefficient
core
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Granted
Application number
CN202010115365.4A
Other languages
Chinese (zh)
Other versions
CN111400869B (en
Inventor
徐向民
邢晓芬
田翔
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
South China University of Technology SCUT
Original Assignee
South China University of Technology SCUT
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by South China University of Technology SCUT filed Critical South China University of Technology SCUT
Priority to CN202010115365.4A priority Critical patent/CN111400869B/en
Publication of CN111400869A publication Critical patent/CN111400869A/en
Application granted granted Critical
Publication of CN111400869B publication Critical patent/CN111400869B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • G—PHYSICS
    • G06—COMPUTING; CALCULATING OR COUNTING
    • G06F—ELECTRIC DIGITAL DATA PROCESSING
    • G06F17/00—Digital computing or data processing equipment or methods, specially adapted for specific functions
    • G06F17/10—Complex mathematical operations
    • G06F17/16—Matrix or vector computation, e.g. matrix-matrix or matrix-vector multiplication, matrix factorization
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/108—Measuring reactor flux
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Physics & Mathematics (AREA)
  • Mathematical Physics (AREA)
  • Pure & Applied Mathematics (AREA)
  • Theoretical Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • Computational Mathematics (AREA)
  • Data Mining & Analysis (AREA)
  • Mathematical Analysis (AREA)
  • Mathematical Optimization (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Algebra (AREA)
  • Computing Systems (AREA)
  • Databases & Information Systems (AREA)
  • Software Systems (AREA)
  • Plasma & Fusion (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention provides a method, a device, a medium and equipment for predicting reactor core neutron flux space-time evolution, wherein the method comprises the following steps: collecting neutron flux calculated values of different reactor core states; preparing an expansion basis function; collecting the measurement value of a detector at the current time of the reactor core; calculating an expansion coefficient at the current moment; fitting the expansion coefficients of each order respectively to obtain a change function of the expansion coefficients along with time; extrapolating the expansion coefficient of each step to obtain an extrapolation value of the expansion coefficient at the subsequent moment; and calculating to obtain a neutron flux prediction result at a subsequent moment according to the expansion coefficient extrapolation value and the expansion basis function. The method can realize the prediction of the neutron flux of the reactor core at the subsequent time and analyze the time-space evolution process of the neutron flux of the reactor core on the basis of the online monitoring result of the neutron flux of the reactor core at the current time and the preceding time so as to ensure the safety of the reactor core of the nuclear reactor.

Description

Reactor core neutron flux space-time evolution prediction method, device, medium and equipment
Technical Field
The invention relates to the technical field of nuclear reactor core operation and safety, in particular to a method, a device, a medium and equipment for predicting reactor core neutron flux space-time evolution.
Background
In the normal operation process of a nuclear reactor, key safety parameters are required to be ensured to meet safety limit values; when the critical safety parameters exceed the limits, the state of the reactor core needs to be confirmed, the influence of accident development is determined through additional safety evaluation, and whether the specified design criteria and safety criteria are met or not is verified. Wherein, the neutron flux in the reactor core is a basic input parameter when calculating the key safety parameter. Therefore, the real-time monitoring and prediction of the neutron flux in the reactor core have important significance for guaranteeing the safety of the reactor core of the nuclear reactor.
At present, various methods, such as a harmonic synthesis method, a simulation correction method, a coupling coefficient method, a polynomial expansion method, a weight factor method and the like, are used at home and abroad to realize the real-time monitoring of neutron flux in a single stable reactor core state. The method realizes real-time monitoring of reactor core power distribution or neutron flux by solving the real-time state of the reactor core and combining neutron detectors inside and outside the reactor and thermocouple measurement signals and the like. However, these methods only consider spatial effects and do not consider temporal evolution for core homeostasis during implementation.
Among a plurality of existing reactor core neutron flux real-time monitoring methods, a method based on a function expansion idea can more easily consider the reactor core neutron flux time evolution characteristics in real-time monitoring, and can obtain the expansion basis functions in different modes to enable the expansion basis functions to contain the reactor core time evolution characteristics, for example, a first-order time-varying basis function is added in a harmonic expansion method; the neutron flux in the reactor core at different time points is decomposed by an intrinsic orthogonal decomposition technology to obtain an expansion basis function containing more time characteristics and the like.
However, on the one hand, the effect and the applicability of the improved methods are required to be further verified and confirmed, and on the other hand, the improved methods are still only aimed at on-line monitoring of the neutron flux in the reactor core, but not a neutron flux space-time evolution prediction method.
Accordingly, the prior art is in need of improvement and development.
Disclosure of Invention
The invention aims to overcome the defects and shortcomings in the prior art, and provides a method, a device, a medium and equipment for predicting the reactor core neutron flux time-space evolution.
In order to achieve the purpose, the invention is realized by the following technical scheme: a reactor core neutron flux space-time evolution prediction method is characterized by comprising the following steps: the method comprises the following steps:
s1, collecting neutron flux calculation values phi (r, t) of different reactor core statesn) Where r represents a spatial position, N1, 2.., N being the number of different core states;
s2, calculating the value phi (r, t) of N neutron fluxesn) Orthogonal decomposition is carried out on the formed matrix to obtain orthogonal basis so as to obtain an expansion basis function
Figure BDA0002391326570000027
n＝1,2,...,N；
S3, collecting the current time detector measurement value S (r) of the reactor cored,ti) Wherein r isdD is the detector position, D is the number of detectors, t is 1,2iThe current time when the reactor core is actually operated;
s4, according to the current time of the reactor core, the detector measurement value S (r)d,ti) And unfolding the basis functions
Figure BDA0002391326570000028
Calculating the expansion coefficient a of the current timen(ti)，n＝1,2,...,N；
S5, expansion coefficient a according to current timen(ti) And the expansion coefficient a of the preceding timen(t0),an(t1),...,an(ti-1) Fitting the expansion coefficient of each order to obtain the time-varying function of the expansion coefficient
Figure BDA0002391326570000021
n＝1,2,...,N；
S6, according to the time variation function of the expansion coefficient
Figure BDA0002391326570000022
Extrapolating the expansion coefficient of each order to obtain the extrapolated value of the expansion coefficient at the subsequent time
Figure BDA0002391326570000023
m≥1；
S7, extrapolating the value according to the expansion coefficient
Figure BDA0002391326570000024
And unfolding the basis functions
Figure BDA0002391326570000025
Calculating to obtain neutron flux prediction result of subsequent time
Figure BDA0002391326570000026
Preferably, the neutron flux calculation value in step S1 is obtained by simulating different core states calculated by the current core by the core fuel management program, and the neutron flux calculation value is acquired at different times tnCalculated neutron flux of phi (r, t)n)。
Preferably, in step S1, the core conditions include core average burnup, boron concentration, power level, and control rod position.
Preferably, in step S5, the fitting of the expansion coefficients of each order is a polynomial fitting.
Preferably, in step S7, the neutron flux prediction result is:
Figure BDA0002391326570000031
a reactor core neutron flux space-time evolution prediction device is characterized in that: the method comprises the following steps:
a data collection module for collecting neutron flux calculation value phi (r, t) of different reactor core statesn) N, N is the number of different core states;
an expansion base preparation module for calculating the value phi (r, t) of N neutron fluxesn) Orthogonal decomposition is carried out on the formed matrix to obtain orthogonal basis so as to obtain an expansion basis function
Figure BDA0002391326570000032
n＝1,2,...,N；
A real-time data acquisition module for acquiring the measured value s (r) of the detector at the current time of the reactor cored,ti) D1, 2, D is the number of detectors, tiThe current time when the reactor core is actually operated;
a processing module for measuring the value s (r) of the detector at the current time of the reactor cored,ti) And unfolding the basis functions
Figure BDA0002391326570000038
Calculating the expansion coefficient a of the current timen(ti) N is 1,2,. cndot.n; according to the expansion coefficient a of the current timen(ti) And the expansion coefficient a of the preceding timen(t0),an(t1),...,an(ti-1) Fitting the expansion coefficient of each order to obtain the time-varying function of the expansion coefficient
Figure BDA0002391326570000039
N is 1,2,. cndot.n; according to the function of the expansion coefficient with time
Figure BDA0002391326570000033
Extrapolating the expansion coefficient of each order to obtain the extrapolated value of the expansion coefficient at the subsequent time
Figure BDA0002391326570000034
m≥1；
A prediction module for extrapolating a value according to the expansion coefficient
Figure BDA0002391326570000035
And unfolding the basis functions
Figure BDA0002391326570000036
Calculating to obtain neutron flux prediction result of subsequent time
Figure BDA0002391326570000037
A storage medium having stored thereon a computer program which, when executed by a processor, causes the processor to carry out the above-described method of predicting the spatio-temporal evolution of neutron flux in a core.
A computing apparatus comprising a processor and a memory for storing a program executable by the processor, wherein the processor, when executing the program stored in the memory, implements the method for predicting the spatial-temporal evolution of neutron flux in an core as described above.
Compared with the prior art, the invention has the following advantages and beneficial effects:
1. by applying orthogonal decomposition and basis function expansion technologies and combining fitting and extrapolation of expansion coefficients, the method not only can realize online monitoring of the neutron flux of the reactor core at the current moment, but also can realize prediction of the neutron flux of the reactor core at the subsequent moment, and realizes prediction of the time-space evolution of the neutron flux of the reactor core on the basis of the prior art and the method; the prediction result can be subsequently used for the safety judgment of the nuclear reactor core so as to ensure the safety of the nuclear reactor core;
2. the neutron flux unfolding basis function can simultaneously comprise the spatial characteristics of three-dimensional neutron fluxes in different reactor core states, namely at different moments, and has the characteristics of time and space evolution;
3. the neutron flux expansion coefficient is related to time, is fitted into a function of time and is extrapolated, and the neutron flux time-space evolution characteristic of the reactor core can be predicted by combining the expansion basis function;
4. the neutron flux expansion basis function is prepared in advance, only the solution, fitting and extrapolation of the expansion coefficient are needed when the reactor core runs, and the calculation speed is high and the time is short.
Drawings
FIG. 1 is a flow chart of a method for predicting the neutron flux spatial-temporal evolution of a reactor core according to the invention;
FIG. 2 is a schematic diagram of an exemplary PWR core assembly arrangement in accordance with an embodiment of the invention;
FIG. 3 is a graph showing the results of fitting and extrapolating expansion coefficients of order 1 for an embodiment used in the present invention;
FIG. 4 is a graph showing the results of 7 th order expansion coefficient fitting and extrapolation for an embodiment of the present invention.
Detailed Description
The present invention will be described in further detail with reference to the accompanying drawings and specific embodiments.
Example one
As shown in fig. 1, fig. 1 is a flow chart of a method for predicting the neutron flux spatial-temporal evolution in a reactor core, which comprises the following steps:
s1, collecting neutron flux calculation values phi (r, t) of different reactor core statesn) Where r represents a spatial position, N1, 2.., N being the number of different core states; the core state refers to average fuel consumption, boron concentration, power level and control rod position of the core, and corresponds to different time tn；
S2, calculating the N neutron fluxes collected in the step S1 to obtain a calculated value phi (r, t)n) Composed matrix
Figure BDA0002391326570000051
Performing orthogonal decomposition, wherein R is the number of spatial positions of neutron flux to obtain orthogonal basis to obtain an expansion basis function
Figure BDA0002391326570000052
N is 1,2,. cndot.n; unfolding basis functions
Figure BDA0002391326570000053
Preparing and storing in advance for later use;
s3, collecting the current time detector measurement value S (r) of the reactor cored,ti) Wherein r isdD is the detector position, D is 1,2Number, tiThe current time when the reactor core is actually operated;
s4, according to the current core time detector measured value S (r) collected in the step S3d,ti) And step S2 preparing the expansion basis function in advance
Figure BDA0002391326570000054
Simultaneous solving of relation equation set of measured value and expansion basis function of each position detector
Figure BDA0002391326570000055
Calculating the expansion coefficient a of the current timen(ti)，n＝1,2,...,N；
S5, calculating the expansion coefficient a of the current time according to the step S4n(ti) And the expansion coefficient a calculated from the preceding timen(t0),an(t1),...,an(ti-1) Fitting expansion coefficients of each order separately
Figure BDA0002391326570000056
Calculation of c0,c1,c2,., obtaining the variation function of the expansion coefficient along with the time
Figure BDA0002391326570000057
n＝1,2,...,N；
S6, obtaining the time-varying function of the expansion coefficient according to the step S5
Figure BDA0002391326570000061
Extrapolating the expansion coefficient of each order to obtain the extrapolated value of the expansion coefficient at the subsequent time
Figure BDA0002391326570000062
m≥1；
S7, extrapolating the value according to the expansion coefficient obtained in the step S6
Figure BDA0002391326570000063
And the expansion obtained in step S2Basis functions
Figure BDA0002391326570000064
Calculating to obtain neutron flux prediction result of subsequent time
Figure BDA0002391326570000065
Compared with the prior art, the reactor core neutron flux space-time evolution prediction method is based on the expansion of the neutron flux function, the solution of the expansion basis function adopts a preparation-in-advance mode, the key point is the fitting and extrapolation of the time-related expansion coefficient, the purpose of obtaining the reactor core neutron flux space-time evolution prediction result is achieved, and the method has the following outstanding advantages:
1) the neutron flux unfolding basis function can simultaneously comprise the spatial characteristics of three-dimensional neutron fluxes in different reactor core states, namely at different moments, and has the characteristics of time and space evolution;
2) the neutron flux expansion coefficient is related to time, is fitted into a function of time and is extrapolated, and the neutron flux time-space evolution characteristic of the reactor core can be predicted by combining the expansion basis function;
3) the neutron flux expansion basis function is prepared in advance, only the solution, fitting and extrapolation of the expansion coefficient are needed when the reactor core runs, and the calculation speed is high and the time is short.
In a specific embodiment of the method for predicting the neutron flux time-space evolution in the reactor core, specifically, the neutron flux calculated value in the step S1 is a neutron flux calculated value in different reactor core states calculated by a reactor core fuel management program simulating a current reactor core.
In the step S2, the matrix composed of neutron fluxes is subjected to orthogonal decomposition, and the method of orthogonal decomposition is not limited in the present invention, and only the orthogonal basis, i.e., the unfolded basis function, is obtained, and the unfolded basis function is prepared and stored in advance before the on-line monitoring and prediction of the neutron fluxes in the reactor core, and does not need to be calculated on site in real time.
In step S4, the focus is to calculate the expansion coefficient of the core at the current time to facilitate the fitting and extrapolation in the subsequent steps, rather than the purpose of solving the online monitoring result of the neutron flux or power distribution in the core as described in other methods or inventions, which is different from the other inventions.
In the step S5, fitting the expansion coefficients according to the expansion coefficients at the current time and the expansion coefficients at the preceding time of the reactor core is performed, but the present invention does not limit the method of function fitting, but proposes to select a polynomial fitting according to the variation trend and the range of the expansion coefficients, and selects 2 to 3 orders for the highest order of the polynomial fitting.
In step S6, when the expansion coefficient is extrapolated for the subsequent time according to the expansion coefficient function fitting result, the extrapolation time step and the number are not limited, but the extrapolation that is too long will result in accumulated deviation.
In order to verify the effectiveness of the method for predicting the neutron flux spatial-temporal evolution of the reactor core, a typical PWR reactor core design verification example is adopted, a typical PWR reactor core assembly arrangement schematic diagram of the embodiment used in the invention is shown in FIG. 2, and different fuel enrichment degrees are represented in different shading modes in the diagram.
According to the method, the neutron flux space-time evolution of the reactor core is predicted, and the current time of the reactor core is t9The current core state is average burnup 4800MWd/tU, critical boron concentration, relative power 100%, and control rods are all extracted from the core; preamble time t1-t8The corresponding core states are that the average fuel consumption of the core is 4000 MWd/tU-4700 MWd/tU, the interval is 100MWd/tU, the critical boron concentration and the relative power are 100 percent, and all control rods are provided.
Expansion coefficient a of each order according to current time and preorder timen(t1),an(t2),...,an(t9) N is 1,2,.. times.n, and each order of expansion coefficient function fitting is performed by using a second order polynomial, namely, an(t)＝c0+c1t+c2t2And performing expansion coefficient extrapolation to calculate t10-t13The expansion coefficient at the moment corresponds to the core state,the average fuel consumption of the reactor core is 4800 MWd/tU-5100 MWd/tU interval of 100MWd/tU, the critical boron concentration and the relative power are 100 percent, and control rods are all provided.
Fig. 3 and 4 are schematic diagrams showing the fitting or extrapolation results of the expansion coefficients of order 1 and 7. Therefore, the change of the expansion coefficient (1) along with time accords with linear (1 st order) and second order (7 th order) rules, and the function fitting is easy to carry out; (2) the expansion coefficient extrapolation is easy to carry out; (3) the time of expansion coefficient extrapolation is not too much, and the accumulation of deviation is reduced.
Predicting reactor core three-dimensional neutron flux by using extrapolated expansion coefficient, t10The deviation of the prediction result at the moment and the real result is small, the deviation of the three-dimensional neutron flux is 0.5%, the radial deviation is 0.07%, and the axial deviation is 0.04%; for the t-th13At time points, the errors of the predicted results and the actual results of the three-dimensional, radial and axial distributions are increased to 2.5%, 1% and 0.15%, respectively. The method for predicting the neutron flux space-time evolution in the reactor core has good effect.
Example two
In order to implement the embodiment, a method for predicting the neutron flux spatial-temporal evolution in a reactor core is provided, in this embodiment, a device for predicting the neutron flux spatial-temporal evolution in a reactor core includes:
a data collection module for collecting neutron flux calculation value phi (r, t) of different reactor core statesn) N, N is the number of different core states;
an expansion base preparation module for calculating the value phi (r, t) of N neutron fluxesn) Orthogonal decomposition is carried out on the formed matrix to obtain orthogonal basis so as to obtain an expansion basis function
Figure BDA0002391326570000083
n＝1,2,...,N；
A real-time data acquisition module for acquiring the measured value s (r) of the detector at the current time of the reactor cored,ti) D1, 2, D is the number of detectors, tiThe current time when the reactor core is actually operated;
a processing module for measuring the value s (r) of the detector at the current time of the reactor cored,ti) And unfolding the basis functions
Figure BDA0002391326570000084
Calculating the expansion coefficient a of the current timen(ti) N is 1,2,. cndot.n; according to the expansion coefficient a of the current timen(ti) And the expansion coefficient a of the preceding timen(t0),an(t1),...,an(ti-1) Fitting the expansion coefficient of each order to obtain the time-varying function of the expansion coefficient
Figure BDA0002391326570000081
N is 1,2,. cndot.n; according to the function of the expansion coefficient with time
Figure BDA0002391326570000082
Extrapolating the expansion coefficient of each order to obtain the extrapolated value of the expansion coefficient at the subsequent time
Figure BDA0002391326570000091
m≥1；
A prediction module for extrapolating a value according to the expansion coefficient
Figure BDA0002391326570000092
And unfolding the basis functions
Figure BDA0002391326570000094
Calculating to obtain neutron flux prediction result of subsequent time
Figure BDA0002391326570000093
EXAMPLE III
The present embodiment provides a storage medium having a computer program stored thereon, which when executed by a processor causes the processor to perform the method for predicting the spatial-temporal evolution of neutron flux in a core according to the first embodiment.
Example four
The embodiment provides a computing device, which comprises a processor and a memory for storing a program executable by the processor, and is characterized in that when the processor executes the program stored in the memory, the method for predicting the neutron flux spatial-temporal evolution in the core according to the first embodiment is implemented.
The above embodiments are preferred embodiments of the present invention, but the present invention is not limited to the above embodiments, and any other changes, modifications, substitutions, combinations, and simplifications which do not depart from the spirit and principle of the present invention should be construed as equivalents thereof, and all such changes, modifications, substitutions, combinations, and simplifications are intended to be included in the scope of the present invention.

Claims (8)

1. A reactor core neutron flux space-time evolution prediction method is characterized by comprising the following steps: the method comprises the following steps:
s1, collecting neutron flux calculation values phi (r, t) of different reactor core statesn) Where r represents a spatial position, N1, 2.., N being the number of different core states;
s2, calculating the value phi (r, t) of N neutron fluxesn) Orthogonal decomposition is carried out on the formed matrix to obtain orthogonal basis so as to obtain an expansion basis function
Figure FDA0002391326560000011
S3, collecting the current time detector measurement value S (r) of the reactor cored,ti) Wherein r isdD is the detector position, D is the number of detectors, t is 1,2iThe current time when the reactor core is actually operated;
s4, according to the current time of the reactor core, the detector measurement value S (r)d,ti) And unfolding the basis functions
Figure FDA0002391326560000012
Calculating the expansion coefficient a of the current timen(ti)，n＝1,2,...,N；
S5, expansion coefficient a according to current timen(ti) And the expansion coefficient a of the preceding timen(t0),an(t1),...,an(ti-1) Fitting the expansion coefficient of each order to obtain the time-varying function of the expansion coefficient
Figure FDA0002391326560000013
S6, according to the time variation function of the expansion coefficient
Figure FDA0002391326560000014
Extrapolating the expansion coefficient of each order to obtain the extrapolated value of the expansion coefficient at the subsequent time
Figure FDA0002391326560000015
S7, extrapolating the value according to the expansion coefficient
Figure FDA0002391326560000016
And unfolding the basis functions
Figure FDA0002391326560000017
Calculating to obtain neutron flux prediction result of subsequent time
Figure FDA0002391326560000018
2. The method for predicting the temporal and spatial evolution of neutron flux in an reactor core according to claim 1, wherein: the neutron flux calculated value in the step S1 is obtained by simulating different core states calculated by the current core by the core fuel management program, and acquiring different times tnCalculated neutron flux of phi (r, t)n)。
3. The method for predicting the temporal and spatial evolution of neutron flux in an reactor core according to claim 1, wherein: in step S1, the core conditions include core average burnup, boron concentration, power level, and control rod position.
4. The method for predicting the temporal and spatial evolution of neutron flux in an reactor core according to claim 1, wherein: in step S5, a polynomial fitting is used to fit the expansion coefficients of each order.
5. The method for predicting the temporal and spatial evolution of neutron flux in an reactor core according to claim 1, wherein: in step S7, the neutron flux prediction result is:
Figure FDA0002391326560000021
6. a reactor core neutron flux space-time evolution prediction device is characterized in that: the method comprises the following steps:
a data collection module for collecting neutron flux calculation value phi (r, t) of different reactor core statesn) N, N is the number of different core states;
an expansion base preparation module for calculating the value phi (r, t) of N neutron fluxesn) Orthogonal decomposition is carried out on the formed matrix to obtain orthogonal basis so as to obtain an expansion basis function
Figure FDA0002391326560000022
A real-time data acquisition module for acquiring the measured value s (r) of the detector at the current time of the reactor cored,ti) D1, 2, D is the number of detectors, tiThe current time when the reactor core is actually operated;
a processing module for measuring the value s (r) of the detector at the current time of the reactor cored,ti) And unfolding the basis functions
Figure FDA0002391326560000023
Calculating the expansion coefficient a of the current timen(ti) N is 1,2,. cndot.n; according to the expansion coefficient a of the current timen(ti) And the expansion coefficient a of the preceding timen(t0),an(t1),...,an(ti-1) Separately for each order of expansion coefficientLine fitting to obtain the time-dependent variation function of the expansion coefficient
Figure FDA0002391326560000024
According to the function of the expansion coefficient with time
Figure FDA0002391326560000025
Extrapolating the expansion coefficient of each order to obtain the extrapolated value of the expansion coefficient at the subsequent time
Figure FDA0002391326560000026
A prediction module for extrapolating a value according to the expansion coefficient
Figure FDA0002391326560000027
And unfolding the basis functions
Figure FDA0002391326560000028
Calculating to obtain neutron flux prediction result of subsequent time
Figure FDA0002391326560000029
7. A storage medium having stored thereon a computer program which, when executed by a processor, causes the processor to carry out the method of predicting spatiotemporal evolution of neutron flux in an core according to any one of claims 1 to 5.
8. A computing device comprising a processor and a memory for storing processor-executable programs, wherein the processor, when executing a program stored in the memory, implements the method for predicting neutron flux spatial-temporal evolution in an core of any of claims 1 to 5.
CN202010115365.4A 2020-02-25 2020-02-25 Reactor core neutron flux space-time evolution prediction method, device, medium and equipment Active CN111400869B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202010115365.4A CN111400869B (en) 2020-02-25 2020-02-25 Reactor core neutron flux space-time evolution prediction method, device, medium and equipment

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202010115365.4A CN111400869B (en) 2020-02-25 2020-02-25 Reactor core neutron flux space-time evolution prediction method, device, medium and equipment

Publications (2)

Publication Number Publication Date
CN111400869A true CN111400869A (en) 2020-07-10
CN111400869B CN111400869B (en) 2022-07-26

Family

ID=71434040

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202010115365.4A Active CN111400869B (en) 2020-02-25 2020-02-25 Reactor core neutron flux space-time evolution prediction method, device, medium and equipment

Country Status (1)

Country Link
CN (1) CN111400869B (en)

Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4642213A (en) * 1984-07-27 1987-02-10 Westinghouse Electric Corp. Anticipatory control of xenon in a pressurized water reactor
US20040091119A1 (en) * 2002-11-08 2004-05-13 Ramani Duraiswami Method for measurement of head related transfer functions
US20100284503A1 (en) * 2008-04-03 2010-11-11 Ge-Hitachi Nuclear Energy Americas Llc Radioisotope production structures, fuel assemblies having the same, and methods of using the same
CN106780592A (en) * 2016-06-30 2017-05-31 华南理工大学 Kinect depth reconstruction algorithms based on camera motion and image light and shade
CN109830317A (en) * 2019-01-29 2019-05-31 中山大学 A kind of core power Proper Orthogonal decomposition on-line reorganization method calculated based on tracking
CN109859867A (en) * 2019-01-29 2019-06-07 中山大学 A kind of reactor core three-dimensional neutron flux Real-time Reconstruction method decomposed based on Proper Orthogonal
US20190180885A1 (en) * 2017-12-12 2019-06-13 Westinghouse Electric Company Llc Subcritical core reactivity bias projection technique

Patent Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4642213A (en) * 1984-07-27 1987-02-10 Westinghouse Electric Corp. Anticipatory control of xenon in a pressurized water reactor
US20040091119A1 (en) * 2002-11-08 2004-05-13 Ramani Duraiswami Method for measurement of head related transfer functions
US20100284503A1 (en) * 2008-04-03 2010-11-11 Ge-Hitachi Nuclear Energy Americas Llc Radioisotope production structures, fuel assemblies having the same, and methods of using the same
CN106780592A (en) * 2016-06-30 2017-05-31 华南理工大学 Kinect depth reconstruction algorithms based on camera motion and image light and shade
US20190180885A1 (en) * 2017-12-12 2019-06-13 Westinghouse Electric Company Llc Subcritical core reactivity bias projection technique
CN109830317A (en) * 2019-01-29 2019-05-31 中山大学 A kind of core power Proper Orthogonal decomposition on-line reorganization method calculated based on tracking
CN109859867A (en) * 2019-01-29 2019-06-07 中山大学 A kind of reactor core three-dimensional neutron flux Real-time Reconstruction method decomposed based on Proper Orthogonal

Non-Patent Citations (3)

* Cited by examiner, † Cited by third party
Title
ANDREW E.JOHNSON等: ""A Transport-Free Method for Predicting the Post-Depletion Spatial Neutron Flux Distribution"", 《NUCLEAR SCIENCE AND ENGINEERING》 *
孙伟等: ""三维多群六角形几何中子扩散程序开发"", 《原子能科学技术》 *
郑友琦等: "基于非线性迭代的压水堆瞬态计算程序开发", 《强激光与粒子束》 *

Also Published As

Publication number Publication date
CN111400869B (en) 2022-07-26

Similar Documents

Publication Publication Date Title
JP5357389B2 (en) How to determine the margin to the operational limit for reactor operation
CN110689974B (en) Improved reactor core power distribution measuring method based on instantaneous gamma response correction
CN110739091A (en) nuclear power plant subcritical degree direct measurement system, hardware platform and measurement method
CN111814343A (en) Reactor core power distribution online reconstruction method for comprehensive in-reactor and out-reactor detector measurement values
CN113312791B (en) Reactor neutron noise analysis method and system based on SP3 equation
Perfetti et al. Development of a SCALE Tool for Continuous–Energy Eigenvalue Sensitivity Coefficient Calculations
CN111400869B (en) Reactor core neutron flux space-time evolution prediction method, device, medium and equipment
CN111898066B (en) Reactor core xenon concentration distribution prediction method based on intrinsic orthogonal decomposition
JP4918345B2 (en) Subcriticality measuring method, subcriticality measuring program, and subcriticality measuring apparatus
CN109861293B (en) Method for evaluating influence of photovoltaic uncertainty on small signal stability of power system
CN113987784B (en) Method and device for quantifying uncertainty of acquisition of pressurized water reactor nuclear design software package
Hu et al. Reliability research for PV system using BDD-based fault tree analysis
Li et al. Development and validation of a PWR on-line power-distribution monitoring system NECP-ONION
Gesh A Graphite Isotope Ratio Method: A Primer on Estimating Plutonium Production in Graphite Moderated Reactors
JP2001133581A (en) Reactor core performance calculating method and apparatus
CN113936823A (en) Method, system and device for acquiring scale coefficient of off-stack detector and storage medium
JP2000162364A (en) Device for calculating reactor core performance of reactor
JPH11337677A (en) Performance calculator for reactor core
CN111797509B (en) Reactor core neutron flux prediction method based on detector measurement value
Farkas et al. WWER-440 criticality calculations using MCNP5 code
Kotlyar et al. One-Group Cross-Section Generation for Monte Carlo Burnup Codes: Multigroup Method Extension and Verification
JPH1123787A (en) Planning method for operating nuclear power station and reactor, and planning device therefor
JPH1020072A (en) Reactor core performance calculating device
JPH06186380A (en) Performance calculator for reactor core
Krayushkin et al. Stochastic effects when determining the maximum RBMK channel power

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant