CN111008350A - Coupling method and system of neutron physical section and thermal hydraulic power and storage medium - Google Patents
Coupling method and system of neutron physical section and thermal hydraulic power and storage medium Download PDFInfo
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Abstract
The invention discloses a coupling method, a coupling system and a storage medium of a neutron physical section and a thermal hydraulic power, wherein the method comprises the following steps: acquiring a measured value of a thermal hydraulic parameter in a current state; determining a change value of the thermal hydraulic parameter based on the reference value and the measured value of the thermal hydraulic parameter; and obtaining a macroscopic cross section of neutrons under a certain specific neutron energy group in the current state for generating a certain type of nuclear reaction based on the change value of the thermal hydraulic parameters and a calculation formula, wherein the calculation formula is a Taylor expansion formula with an independent variable as the thermal hydraulic parameters and a dependent variable as a function of the macroscopic cross section. The invention solves the problem of coupling of the neutron physical section and the thermal hydraulic power under the requirement of high calculation speed, has simple and convenient implementation mode, is suitable for processing modes of a plurality of energy groups and various sections in batches, and has low difficulty in later-stage adaptability modification; moreover, all influence factors in the coupling of the neutron physical section and the thermal hydraulic power of the nuclear reactor can be comprehensively considered, and the method is suitable for scenes with high requirements on range coverage.
Description
Technical Field
The invention relates to the field of nuclear power, in particular to a method and a system for coupling a neutron physical section with thermal hydraulic power and a storage medium.
Background
The interaction of neutrons with matter nuclei is often measured in cross section. The cross-section is actually the probability of some kind of nuclear reaction. The cross-section is divided into a macroscopic cross-section Σ and a microscopic cross-section σ in terms of physical definition, where the macroscopic cross-section Σ represents the probability of a certain type of nuclear reaction of a neutron with all target nuclei within a unit volume, and the microscopic cross-section σ represents the probability of a certain type of nuclear reaction of a target nucleus in the target layer with a neutron in the incident neutron beam having a given average energy. The conversion formula between the macroscopic cross section and the microscopic cross section is Σ ═ N σ. Where N is the target nucleic acid density.
Experiments show that the size of the microscopic section has a relation with the property of target nuclei and the energy of incident neutrons, and a nuclear physicist compiles various sections of nuclear reactions of various nuclides and neutrons with different energies into a database through experiments so as to be applied conveniently.
In a relatively common reactor, there are many materials in the active region and thus many species involved, such as U-235, U-238, hydrogen (H), oxygen (O), iron (Fe), B-10, etc. According to conventional methods, to determine the macroscopic cross-section of a nuclear reaction of all target nucleic acid materials in a unit volume region with neutrons of a given energy, it is necessary to obtain the microscopic cross-section of the nuclear reaction of all single target nucleic acid materials in the region at the energy of the neutrons and to obtain the nuclear density of the nuclides. Where microscopic sections of a nuclear reaction of a single target nucleic acid material at a certain neutron energy need to be looked up in a database. The nuclear density is determined by the material composition and distribution of the various components of the reactor.
In addition, in a common reactor, there are also the following more specific cases: u-238 will cause the width of the resonance absorption cross section peak to change due to the difference of temperature, thereby causing the change of the neutron resonance absorption cross section; water (H2O), heavy water (D2O) or any other coolant is present in liquid form in the reactor, and therefore the density thereof will be different and the density of nuclei thereof will be correspondingly different under different temperature and pressure conditions; boron (B-10) is dissolved in water in the form of boric acid, and thus the difference in density also results in a change in the content of boric acid in the neutron-active region. In short, the temperature pressure density state in the reactor can have great influence on the nuclear density of some key nuclides so as to influence the macroscopic absorption cross section.
Therefore, conventionally, the macroscopic cross section at a specific neutron energy obtained from a specific thermodynamic and hydraulic parameter in a reactor needs to undergo the following processes: determining a nuclear density of the coolant material from the coolant temperature pressure density; determining the nuclear density of the solid material through the materials and the distribution of all parts of the reactor; searching a microscopic section in a data table through given neutron energy and nuclide information; and calculating to obtain a macroscopic section.
This method is accurate enough, but the process is complicated and requires a long time to determine the density of nuclei and to find microscopic sections. The method can be used in the fields of core design, fuel arrangement certainty calculation and the like, but has no operability in the field of real-time simulation with high requirement on calculation speed.
Disclosure of Invention
The technical problem to be solved by the present invention is to provide a method, a system and a storage medium for coupling a neutron physical cross section and a thermal hydraulic power, aiming at the above-mentioned defects of the prior art.
The technical scheme adopted by the invention for solving the technical problems is as follows: a method for coupling a neutron physical section with thermal hydraulic power is constructed, and comprises the following steps:
acquiring a measured value of a thermal hydraulic parameter in a current state;
determining a change value of the thermal hydraulic parameter based on the reference value and the measured value of the thermal hydraulic parameter;
and obtaining a macroscopic cross section of neutrons under a certain specific neutron energy group in the current state for generating a certain type of nuclear reaction based on the change value of the thermal hydraulic parameters and a calculation formula, wherein the calculation formula is a Taylor expansion formula with an independent variable as the thermal hydraulic parameters and a dependent variable as a function of the macroscopic cross section.
Preferably, the thermohydraulic parameters include fuel temperature, coolant temperature, moderator density, boron concentration.
Preferably, the taylor expansion is specifically:
wherein, aixg、bixg、cixg、dixgBeing a predetermined constant, Δ Tf、ΔTM、ΔρM、ΔCBRepresenting the variation values of fuel temperature, coolant temperature, moderator density, boron concentration in the thermohydraulic parameters, ∑xgMacroscopic cross section, Σ, representing a certain type of nuclear reaction occurring in a neutron of a certain neutron energy group in the current state0xgAnd the reference macroscopic cross section corresponding to the thermal hydraulic parameter is the reference value, and n is a positive integer greater than or equal to 2.
Preferably, the method further comprises:
obtaining reference macroscopic cross-sections sigma corresponding to reference values of fuel temperature, coolant temperature, moderator density and boron concentration0xg；
Obtaining reference values of coolant temperature, moderator density, boron concentration and different test values T of fuel temperaturejfCorresponding different macroscopic cross-sections ΣjfxgBased on said sigma0xg、ΣjfxgAnd TjfCalculating to obtain the aixg；
Obtaining reference values of fuel temperature, moderator density, boron concentration and different test values T of coolant temperaturejMCorresponding different macroscopic cross-sections ΣjMxgBased on said sigma0xg、ΣjMxgAnd TjMCalculating to obtain bixg；
Obtaining fuel temperature, coolant temperature, boron concentrationReference value and different test values ρ of moderator densityjMCorresponding different macroscopic cross-sections ΣjρxgBased on said sigma0xg、ΣjρxgAnd ρjMCalculating to obtain cixg；
Obtaining reference values of fuel temperature, coolant temperature, moderator density and different test values C of boron concentrationjBCorresponding different macroscopic cross-sections ΣjCxgBased on said sigma0xg、ΣjCxgAnd CjBCalculating to obtain dixg；
Wherein j sequentially takes n positive integers from 1 to n.
The invention also claims a computer-readable storage medium for storing a computer program, characterized in that the computer program is readable by a processor and performs the method as described above.
The invention also claims a system for coupling a neutron-physical section with a thermohydraulic force, comprising a processor and a memory, said memory storing a computer program readable by the processor and executing the method as described above.
The invention also claims a coupling system of the neutron physical section and the thermal hydraulic power, which comprises:
the thermal hydraulic parameter measured value acquisition unit is used for acquiring the measured value of the thermal hydraulic parameter in the current state;
the thermal hydraulic parameter change value acquisition unit is used for determining the change value of the thermal hydraulic parameter based on the reference value and the measured value of the thermal hydraulic parameter;
and the macroscopic cross section acquisition unit is used for acquiring a macroscopic cross section of a neutron under a certain neutron energy group in a current state, wherein the macroscopic cross section is generated by a certain type of nuclear reaction of the neutron under the certain neutron energy group based on the change value of the thermal hydraulic parameter and a calculation formula, and the calculation formula is a Taylor expansion formula with an independent variable being the thermal hydraulic parameter and a dependent variable being a function of the macroscopic cross section.
Preferably, the thermohydraulic parameters include fuel temperature, coolant temperature, moderator density, boron concentration.
Preferably, the taylor expansion is specifically:
wherein, aixg、bixg、cixg、dixgBeing a predetermined constant, Δ Tf、ΔTM、ΔρM、ΔCBRepresenting the variation values of fuel temperature, coolant temperature, moderator density, boron concentration in the thermohydraulic parameters, ∑xgMacroscopic cross section, Σ, representing a certain type of nuclear reaction occurring in a neutron of a certain neutron energy group in the current state0xgAnd the reference macroscopic cross section corresponding to the thermal hydraulic parameter is the reference value, and n is a positive integer greater than or equal to 2.
Preferably, the system further comprises:
Σxg0a calculation unit for obtaining a reference macroscopic cross-section Σ corresponding to a reference value for fuel temperature, coolant temperature, moderator density, boron concentration0xg；
aixgA calculation unit for obtaining reference values of coolant temperature, moderator density, boron concentration and different test values T of fuel temperaturejfCorresponding different macroscopic cross-sections ΣjfxgBased on said sigmaOxg、ΣjfxgAnd TjfCalculating to obtain the aixg；
bixgA calculation unit for obtaining reference values of fuel temperature, moderator density, boron concentration and different test values T of coolant temperaturejMCorresponding different macroscopic cross-sections ΣjMxgBased on said sigma0xg、ΣjMxgAnd TjMCalculating to obtain bixg；
cixgA calculation unit for obtaining reference values of fuel temperature, coolant temperature, boron concentration and different test values ρ of moderator densityjMCorresponding different macroscopic cross-sections ΣjρxgBased on said sigma0xg、ΣjρxgAnd ρjMCalculating to obtain cixg；
dixgA calculation unit for obtaining reference values of fuel temperature, coolant temperature, moderator density and different test values C of boron concentrationjBCorresponding different macroscopic cross-sections ΣjCxgBased on said sigma0xg、ΣjCxgAnd CjBCalculating to obtain dixg；
Wherein j sequentially takes n positive integers from 1 to n.
The coupling method, the coupling system and the storage medium of the neutron physical section and the thermal hydraulic power have the following beneficial effects: the method solves the problem of coupling of the neutron physical section and the thermal hydraulic power under the requirement of high calculation speed, has simple and convenient implementation mode, can be implemented by using a simple programming language for all application scenes, is suitable for processing modes of a plurality of energy groups and various sections in batches, and has low difficulty in later-stage adaptability modification; moreover, all influence factors in the coupling of the neutron physical section and the thermal hydraulic power of the nuclear reactor can be comprehensively considered, and the method is suitable for scenes with high requirements on range coverage.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to the provided drawings without creative efforts:
FIG. 1 is a flow chart of a method according to a first embodiment of the present invention;
fig. 2 is a schematic structural diagram of a fourth embodiment of the present invention.
Detailed Description
To facilitate an understanding of the invention, the invention will now be described more fully with reference to the accompanying drawings. Exemplary embodiments of the invention are shown in the drawings. This invention may, however, be embodied in many different forms and should not be construed as limited to the embodiments set forth herein. Rather, these embodiments are provided so that this disclosure will be thorough and complete.
Unless defined otherwise, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this invention belongs. The terminology used in the description of the invention herein is for the purpose of describing particular embodiments only and is not intended to be limiting of the invention.
The general idea of the invention is as follows: firstly, acquiring a measured value of a thermal hydraulic parameter in a current state, then determining a change value of the thermal hydraulic parameter based on a reference value and the measured value of the thermal hydraulic parameter, and finally acquiring a macroscopic cross section of neutrons in a certain specific neutron energy group under the current state, wherein the computational formula is a Taylor expansion formula with an independent variable being the thermal hydraulic parameter and a dependent variable being a function of the macroscopic cross section, and the macroscopic cross section is a function of the neutron energy group under the current state.
In order to better understand the technical solutions, the technical solutions will be described in detail below with reference to the drawings and the specific embodiments of the specification, and it should be understood that the embodiments and specific features of the embodiments of the present invention are detailed descriptions of the technical solutions of the present application, and are not limited to the technical solutions of the present application, and the technical features of the embodiments and examples of the present invention may be combined with each other without conflict.
Example one
Before describing the method of the present embodiment, the idea of the present embodiment will be described first. Considering that in a specific reactor, the arrangement and material of the solid members in the reactor are determined and do not change with the change of the thermal hydraulic parameters in the reactor, so that in the case of determining neutron energy, the macroscopic cross section can be considered to be only related to the thermal hydraulic parameters, and other factors become constants, therefore, the calculation of the macroscopic absorption cross section can be written as follows:
Σxg(xi) formula (1)
Wherein, sigmaxgRepresents the macroscopic cross section of the neutron generation x-nuclear reaction with the energy group g, and Xi represents the thermal hydraulic parameters to be considered. The thermo-hydraulic parameters considered in this embodiment include fuel temperature, coolant temperature, moderator density, boron concentration, and therefore, equation (1) can be refined to equation (2):
Σxg＝f(Tf,TM,ρM,CB) Formula (2)
Wherein, sigmaxgRepresents the macroscopic section of the neutron-generating x-nuclear reaction with the energy group g, TfIndicating the fuel temperature, TMDenotes the coolant temperature, pMDenotes moderator density, CBRepresents the boron concentration.
Taylor expansion is performed on the above equation (2), and a reference state is determined, provided that the fuel temperature, the coolant temperature, the moderator density, and the boron concentration in the reference state are respectively TfREF、TMREF、ρMREF、CBREFThe macroscopic section of the neutron generating x-nuclear reaction in the reference state is ∑0xgThus, the formula (2) can be written as formula (3):
equation (3) is simplified to equation (4):
wherein, aixg、bixg、cixg、dixgBeing a predetermined constant, Δ Tf、ΔTM、ΔρM、ΔCBRepresenting the variation values of fuel temperature, coolant temperature, moderator density, boron concentration in the thermohydraulic parameters, ∑xgMacroscopic cross section, Σ, representing a certain type of nuclear reaction occurring in a neutron of a certain neutron energy group in the current state0xgRepresenting a reference macroscopic cross section corresponding to the thermal hydraulic parameter as the reference value, n being greater than or equal to 2The positive integer is generally 2, that is, the requirement can be met by performing taylor expansion for 2 times.
As can be seen from equation (4), a is predeterminedixg、bixg、cixg、dixgThen later only need to obtain Δ Tf、ΔTM、ΔρM、ΔCBIt is only necessary to substitute the formula (4), which is the general idea of the present embodiment. For the parameter Σ in equation (4)0xg、aixg、bixg、cixg、dixgAnd can be obtained by pre-calculation. In particular, for a given n +1 points, according to the theorem of uniqueness of the polynomial difference
If xiTwo by two are different, then only one polynomial y ═ P (x) with degree not exceeding n exists, so that y isi＝P(xi) (i ═ 0, 1.., n) holds. So the use of n-term expansion requires n +1 points that are different two by two. Therefore, after the number n of the expanded terms in the formula (4) is determined, the section parameters under different thermal parameter working conditions can be obtained by a traditional method, and the process is as follows:
1) determining a thermal working condition as a reference state and a section parameter in the reference state as a basic state section parameter, wherein (sigma)0xg,T0f,T0M,ρ0MC0B) Represents;
2) changing TfWhile other thermal parameters are maintained to obtain other TfCross-sectional value of lower, TfThe number of the selected (c) is required to satisfy the principle of n +1, and the following steps are adopted
Represents;
3) changing TMWhile other thermal parameters are maintained to obtain other TMCross-sectional value of lower, TMThe number of the selected (c) is required to satisfy the principle of n +1, and the following steps are adopted
Represents;
4) varying rhoMWhile other thermal parameters are maintained unchanged to obtain other rho valuesMCross-sectional value of pMThe number of the selected (c) is required to satisfy the principle of n +1, and the following steps are adopted
Represents;
5) change CBWhile other thermal parameters are kept unchanged to obtain other CBCross-sectional value ofBThe number of the selected (c) is required to satisfy the principle of n +1, and the following steps are adopted
Represents;
it should be noted here that ∑ is0xgAnd sigma0fxg、Σ0Mxg、Σ0ρxg、Σ0CxgAre in fact equal, so in step 1) it is determined that ∑ is0xgThereafter, for the above steps 2) -5), j may be actually only 1 to n. Therefore, Σ can be directly obtained by step 1)0xgThen, the data of the section value and the thermal parameter value in the step 2) are processed
Substituting equation (4), we can get the equation system of the fuel temperature as:
obviously, the system of equations thereon can be considered as relating to aixgIn which Δ TifRepresents TifAnd T0fThe difference of (a). A is obtained by solving the above equation setixg. Similarly, the corresponding equation set can be obtained for the coolant temperature, the moderator density and the boron concentration, and b can be obtained by solving the equation setixg、cixg、dixgThe value of (c).
According to the above analysis, with reference to fig. 1, the method of the present embodiment includes:
s101, acquiring a measured value of a thermotechnical hydraulic parameter in a current state; preferably, the thermohydraulic parameters include fuel temperature, coolant temperature, moderator density, boron concentration;
s102, determining a change value of the thermal hydraulic parameter based on the reference value and the measured value of the thermal hydraulic parameter;
s103, obtaining a macroscopic cross section of neutrons under a certain specific neutron energy group in the current state, wherein the macroscopic cross section is generated by the neutrons under the certain specific neutron energy group based on the variation value of the thermal hydraulic parameters and a calculation formula, the calculation formula is a Taylor expansion formula with independent variables as the thermal hydraulic parameters and dependent variables as functions of the macroscopic cross section, and the Taylor expansion formula is specifically the formula (4).
It can be seen that, in step S102, the variation Δ T of the thermodynamic and hydraulic parameter can be determined by simple subtractionf、ΔTM、ΔρM、ΔCBThen only Δ T is neededf、ΔTM、ΔρM、ΔCBThe macroscopic cross section of neutrons under a certain specific neutron energy group in the current state and subjected to a certain type of nuclear reaction can be obtained by substituting the equation (4), the calculation speed is high, and the problem of coupling of the neutron physical cross section and thermal hydraulic power under the requirement of high calculation speed is solved.
Preferably, the method of the present embodiment further includes, before the step S101, performing the following steps to determine a in advanceixg、bixg、cixg、dixgConstant value of (2):
s1011, based on other known macroscopic cross section calculation methods, obtaining reference macroscopic cross sections sigma corresponding to reference values of fuel temperature, coolant temperature, moderator density and boron concentration0xg；
S1012, acquiring reference values of coolant temperature, moderator density and boron concentration and different test values T of fuel temperature based on other known macroscopic cross section calculation methodsjfCorresponding different macroscopic cross-sections ΣjfxgBased on said sigma0xg、ΣjfxgAnd TjfCalculating to obtain the aixg；
S1013, calculation method based on other known macroscopic cross sectionsMethod for obtaining reference values for fuel temperature, moderator density, boron concentration and different test values T for coolant temperaturejMCorresponding different macroscopic cross-sections ΣjMxgBased on said sigma0xg、ΣjMxgAnd TjMCalculating to obtain bixg；
S1014, acquiring reference values of fuel temperature, coolant temperature, boron concentration and different test values rho of moderator density based on other known macroscopic cross section calculation methodsjMCorresponding different macroscopic cross-sections ΣjρxgBased on said sigma0xg、ΣjρxgAnd ρjMCalculating to obtain cixg；
S1015, based on other known macroscopic cross section calculation methods, obtaining reference values of fuel temperature, coolant temperature, moderator density and different test values C of boron concentrationjBCorresponding different macroscopic cross-sections ΣjCxgBased on said sigmaOxg、ΣjCxgAnd CjBCalculating to obtain dixg；
Wherein j sequentially takes n positive integers from 1 to n. It should be noted that, the above steps S1012 to S1015 do not have any restriction on the order.
It will be understood by those skilled in the art that all or part of the processes of the methods of the embodiments described above can be implemented by a computer program, which can be stored in a computer-readable storage medium, and when executed, can include the processes of the embodiments of the methods described above. The storage medium may be a magnetic disk, an optical disk, a Read Only Memory (ROM), a Random Access Memory (RAM), or the like.
Example two
Based on the same inventive concept, the second embodiment discloses a computer-readable storage medium for storing a computer program, which can be read by a processor and execute the method according to the first embodiment.
EXAMPLE III
Based on the same inventive concept, the third embodiment discloses a coupling system of a neutron-physical cross section and a thermal hydraulic power, which comprises a processor and a memory, wherein the memory stores a computer program, and the computer program can be read by the processor and executes the method of the first embodiment.
Example four
Referring to fig. 2, based on the same inventive concept, the fourth embodiment discloses a neutron physical cross section and thermal hydraulic coupling system, which includes:
the measured value acquiring unit 201 is configured to acquire a measured value of a hydraulic parameter under a current state, where the hydraulic parameter includes, preferably, a fuel temperature, a coolant temperature, a moderator density, and a boron concentration.
The thermal hydraulic parameter variation value obtaining unit 202 determines a variation value of the thermal hydraulic parameter based on the reference value and the measured value of the thermal hydraulic parameter.
A macroscopic cross section obtaining unit 203, configured to obtain a macroscopic cross section where neutrons in a certain specific neutron energy group generate a certain type of nuclear reaction in the current state based on the variation value of the thermal hydraulic parameter and a calculation formula, where the calculation formula is a taylor expansion formula where an independent variable is the thermal hydraulic parameter and a dependent variable is a function of the macroscopic cross section.
Wherein the Taylor expansion is specifically:
wherein, aixg、bixg、cixg、dixgBeing a predetermined constant, Δ Tf、ΔTM、ΔρM、ΔCBRepresenting the variation values of fuel temperature, coolant temperature, moderator density, boron concentration in the thermohydraulic parameters, ∑xgMacroscopic cross section, Σ, representing a certain type of nuclear reaction occurring in a neutron of a certain neutron energy group in the current state0xgRepresenting the corresponding reference macro section when the thermal hydraulic parameter is the reference valueN is a positive integer of 2 or more.
Preferably, the system further comprises:
Σxg0a calculation unit for obtaining a reference macroscopic cross-section Σ corresponding to a reference value for fuel temperature, coolant temperature, moderator density, boron concentrationOxg；
aixgA calculation unit for obtaining reference values of coolant temperature, moderator density, boron concentration and different test values T of fuel temperaturejfCorresponding different macroscopic cross-sections ΣjfxgBased on said sigma0xg、ΣjfxgAnd TjfCalculating to obtain the aixg；
bixgA calculation unit for obtaining reference values of fuel temperature, moderator density, boron concentration and different test values T of coolant temperaturejMCorresponding different macroscopic cross-sections ΣjMxgBased on said sigma0xg、ΣjMxgAnd TjMCalculating to obtain bixg；
cixgA calculation unit for obtaining reference values of fuel temperature, coolant temperature, boron concentration and different test values ρ of moderator densityjMCorresponding different macroscopic cross-sections ΣjρxgBased on said sigma0xg、ΣjρxgAnd ρjMCalculating to obtain cixg；
dixgA calculation unit for obtaining reference values of fuel temperature, coolant temperature, moderator density and different test values C of boron concentrationjBCorresponding different macroscopic cross-sections ΣjCxgBased on said sigma0xg、ΣjCxgAnd CjBCalculating to obtain dixg；
Wherein j sequentially takes n positive integers from 1 to n.
It is noted that in the above description of the various units, these units are divided for clarity of illustration. However, in actual implementation, the boundaries of the various elements may be fuzzy. For example, any or all of the functional units herein may share various hardware and/or software elements. Also for example, any and/or all of the functional units herein may be implemented in whole or in part by a common processor executing software instructions. Accordingly, the scope of the present invention is not limited by the mandatory boundaries between the various hardware and/or software elements, unless explicitly claimed otherwise.
In summary, the coupling method, system and storage medium for neutron physical cross section and thermal hydraulic power of the invention have the following advantages: the method solves the problem of coupling of the neutron physical section and the thermal hydraulic power under the requirement of high calculation speed, has simple and convenient implementation mode, can be implemented by using a simple programming language for all application scenes, is suitable for processing modes of a plurality of energy groups and various sections in batches, and has low difficulty in later-stage adaptability modification; moreover, all influence factors in the coupling of the neutron physical section and the thermal hydraulic power of the nuclear reactor can be comprehensively considered, and the method is suitable for scenes with high requirements on range coverage.
While the present invention has been described with reference to the embodiments shown in the drawings, the present invention is not limited to the embodiments, which are illustrative and not restrictive, and it will be apparent to those skilled in the art that various changes and modifications can be made therein without departing from the spirit and scope of the invention as defined in the appended claims.
Claims (10)
1. A method for coupling a neutron physical section with a thermal hydraulic power is characterized by comprising the following steps:
acquiring a measured value of a thermal hydraulic parameter in a current state;
determining a change value of the thermal hydraulic parameter based on the reference value and the measured value of the thermal hydraulic parameter;
and obtaining a macroscopic cross section of neutrons under a certain specific neutron energy group in the current state for generating a certain type of nuclear reaction based on the change value of the thermal hydraulic parameters and a calculation formula, wherein the calculation formula is a Taylor expansion formula with an independent variable as the thermal hydraulic parameters and a dependent variable as a function of the macroscopic cross section.
2. The method of claim 1, wherein the thermohydraulic parameters include fuel temperature, coolant temperature, moderator density, and boron concentration.
3. The method for coupling a neutronic-physical cross section with a thermohydraulic force according to claim 2, wherein the taylor expansion is specifically:
wherein, aixg、bixg、cixg、dixgBeing a predetermined constant, Δ Tf、ΔTM、ΔρM、ΔCBRepresents the variation values of fuel temperature, coolant temperature, moderator density and boron concentration in the thermal hydraulic parameters, sigmaxgRepresents the macroscopic section, sigma, of a neutron under a specific neutron energy group in the current state0xgAnd the reference macroscopic cross section corresponding to the thermal hydraulic parameter is the reference value, and n is a positive integer greater than or equal to 2.
4. The method of coupling a neutronic physical section with a thermohydraulic force of claim 3, further comprising:
obtaining the reference macroscopic cross section sigma corresponding to the reference values of the fuel temperature, the coolant temperature, the moderator density and the boron concentration0xg；
Obtaining reference values of coolant temperature, moderator density, boron concentration and different test values T of fuel temperaturejfCorresponding different macroscopic cross-sections ∑jfxgBased on said ∑0xg、∑jfxgAnd TjfCalculating to obtain the aixg；
Obtaining reference values of fuel temperature, moderator density, boron concentration and different test values T of coolant temperaturejMCorresponding to differentMacroscopic section ∑jMxgBased on said ∑0xg、∑jMxgAnd TjMCalculating to obtain bixg；
Obtaining reference values for fuel temperature, coolant temperature, boron concentration, and different test values ρ for moderator densityjMCorresponding different macroscopic cross-sections ∑jρxgBased on said ∑0xg、∑jρxgAnd ρjMCalculating to obtain cixg；
Obtaining reference values of fuel temperature, coolant temperature, moderator density and different test values C of boron concentrationjBCorresponding different macroscopic cross-sections ∑jCxgBased on said ∑0xg、∑jCxgAnd CjBCalculating to obtain dixg；
Wherein j sequentially takes n positive integers from 1 to n.
5. A computer-readable storage medium for storing a computer program, wherein the computer program is readable by a processor and performs the method according to any one of claims 1-5.
6. A system for coupling a neutronic-physical cross-section with a thermo-hydraulic force, comprising a processor and a memory, said memory storing a computer program readable by the processor and adapted to perform the method of any of claims 1-5.
7. A system for coupling a neutron-physical cross section with a thermal hydraulic power is characterized by comprising:
the thermal hydraulic parameter measured value acquisition unit is used for acquiring the measured value of the thermal hydraulic parameter in the current state;
the thermal hydraulic parameter change value acquisition unit is used for determining the change value of the thermal hydraulic parameter based on the reference value and the measured value of the thermal hydraulic parameter;
and the macroscopic cross section acquisition unit is used for acquiring a macroscopic cross section of a neutron under a certain neutron energy group in a current state, wherein the macroscopic cross section is generated by a certain type of nuclear reaction of the neutron under the certain neutron energy group based on the change value of the thermal hydraulic parameter and a calculation formula, and the calculation formula is a Taylor expansion formula with an independent variable being the thermal hydraulic parameter and a dependent variable being a function of the macroscopic cross section.
8. The system of claim 7, wherein the thermohydraulic parameters include fuel temperature, coolant temperature, moderator density, and boron concentration.
9. The system for coupling a neutronic-physical cross section with a thermohydraulic force of claim 8, wherein the taylor expansion is specifically:
wherein, aixg、bixg、cixg、dixgBeing a predetermined constant, Δ Tf、ΔTM、ΔρM、ΔCBRepresents the variation values of fuel temperature, coolant temperature, moderator density and boron concentration in the thermal hydraulic parameters, sigmaxgRepresents the macroscopic section, sigma, of a neutron under a specific neutron energy group in the current state0xgAnd the reference macroscopic cross section corresponding to the thermal hydraulic parameter is the reference value, and n is a positive integer greater than or equal to 2.
10. The system for coupling a neutronic physical section with a thermohydraulic force of claim 9, further comprising:
∑xg0a computing unit for obtaining a reference macroscopic cross section sigma corresponding to reference values of fuel temperature, coolant temperature, moderator density and boron concentration0xg；
aixgA calculation unit for obtaining reference values of coolant temperature, moderator density, boron concentration and different test values T of fuel temperaturejfCorrespond toIs different in macroscopic cross section ∑jfxgBased on said ∑0xg、∑jfxgAnd TjfCalculating to obtain the aixg；
bixgA calculation unit for obtaining reference values of fuel temperature, moderator density, boron concentration and different test values T of coolant temperaturejMCorresponding different macroscopic cross-sections ∑jMxgBased on said ∑0xg、∑jMxgAnd TjMCalculating to obtain bixg；
cixgA calculation unit for obtaining reference values of fuel temperature, coolant temperature, boron concentration and different test values ρ of moderator densityjMCorresponding different macroscopic cross-sections ∑jρxgBased on said ∑0xg、∑jρxgAnd ρjMCalculating to obtain cixg；
dixgA calculation unit for obtaining reference values of fuel temperature, coolant temperature, moderator density and different test values C of boron concentrationjBCorresponding different macroscopic cross-sections ∑jCxgBased on said ∑0xg、∑jCxgAnd CjBCalculating to obtain dixg；
Wherein j sequentially takes n positive integers from 1 to n.
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