CN107038294A - For the Resonance self-shielding computational methods based on equivalent one-dimensional rod model of light water reactor - Google Patents
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Abstract
For the Resonance self-shielding computational methods based on equivalent one-dimensional rod model of light water reactor, 1, the Resonance self-shielding computational problem for light water reactor, the Dan Kefu modifying factors of each fuel rod are calculated using neutron current method；2nd, according to Dan Kefu modifying factors and the functional relation of one-dimensional rod moderator external diameter, in the case of known Dan Kefu modifying factors, moderator external diameter is obtained using binary chop method；3rd, equivalent one-dimensional fuel rod is calculated using subgroup method or ultra-fine group's method, obtain each circle of fuel rod effectively shields section certainly；Compared to traditional Resonance self-shielding computational methods, the problem of present invention can calculate complex geometry with higher computational efficiency, and can obtain the effective from screen section of space correlation.
Description
Technical field
The present invention relates to nuclear reactor design and security technology area, and in particular to it is a kind of for light water reactor based on
The Resonance self-shielding computational methods of equivalent one-dimensional rod model.
Background technology
Traditional light water reactor in-core fuel management calculates and typically uses two-step method, i.e., obtain few group by Assembly calculation first
Constant, then the data such as reactivity, critical boron concentration for obtaining reactor core etc. and power distribution are calculated by reactor core.But this method
The problems such as error and history effect of spatial homogenization can be introduced, therefore the high-fidelity calculating of Whole core one-step method is obtained in recent years
Pay attention to.One-step method refers to not do homogenization spatially, is directly calculated by the Resonance self-shielding of full heap yardstick, transports calculating and fire
Consumption calculating obtains the data such as reactivity, critical boron concentration etc. and power distribution.The precision of this method has very compared to two-step method
Big raising, but challenge is proposed to existing Resonance self-shielding computational methods simultaneously.The yardstick of heap complete first is very big, therefore it is required that
Resonance self-shielding computational methods have higher efficiency；Then it is required to handle the complex geometry in reactor core；Finally require to obtain
Accurately the effective of space correlation effectively shields section certainly from the screen each circle of section, i.e. fuel rod.
Existing Resonance self-shielding computational methods are broadly divided into equivalent theoretical, subgroup method and the ultra-fine class of group's method three.It is of equal value
Theory is broadly divided into the calculating of lattice cell effective resonance integral and Dan Kefu corrects two steps.When calculating lattice cell effective resonance integral,
Scattering source item is simplified using narrow resonance approximation, rational approximation is used to the first collision probability of lattice cell, by the solution of lattice cell
Analysis power spectrum is write as the parsing power spectrum identical form with homogeneous system, and then the resonance integral of lattice cell is of equal value into one or more
The weight sum of homogeneous system resonance integral.The resonance integral of homogeneous system can make the form of form and be stored in multigroup number
According to only needing to enter row interpolation according to coefficient in storehouse, during calculating, therefore with very high efficiency.Dan Kefu modifying factors are typically adopted
Calculated with neutron current method, neutron current transports method for solving using multigroup and calculated, it is adaptable to the calculating of complicated geometry.It is all common
Energy group shake only using a Dan Kefu modifying factor, computational efficiency is higher, it is adaptable to the calculating of large scale problem.But reason of equal value
By the averga cross section using Dan Kefu modifying factor amendment fuel rods, it is impossible to obtain the section of space correlation.Subgroup method is to cutting
Face size carries out the division of subgroup, by the integration to Continuous Energy transport equation on subgroup, obtains subgroup stationary source equation.
Because subgroup stationary source equation is similar to multigroup transport equation, method for solving can be transported using ripe multigroup and it is solved,
Therefore subgroup method can be used for the calculating of full heap in theory, the problem of can solve the problem that complex geometry and obtain space correlation
Effectively from screen section.But be due to that the multigroup of full heap yardstick transports calculating and taken very much, and subgroup method need to solve it is multiple
Multigroup transport equation, therefore the Resonance self-shielding computational efficiency that subgroup method directly is applied into full heap is relatively low.Ultra-fine group's method pair
Energy variable carries out the division of ultra-fine group, moderation of neutrons equation is solved on the basis of ultra-fine group, with very high precision.But
Be ultra-fine group amount of calculation it is very big, it is impossible to be directly used in full heap Resonance self-shielding calculate.
Therefore existing three kinds of methods all cannot be directly used to the Resonance self-shielding of full heap and calculate, it is necessary to study a kind of new
Resonance self-shielding computational methods solve the challenge that one-step method is brought.
The content of the invention
In order to overcome the problem of above-mentioned prior art is present, it is an object of the invention to provide a kind of base for light water reactor
In the Resonance self-shielding computational methods of equivalent one-dimensional rod model, this method is transported solver using multigroup and calculated using neutron current method
The Dan Kefu modifying factors of fuel rod；The equivalence defined with collision probability is defined using the neutron current of Dan Kefu modifying factors,
In the case of known fuel rod Dan Kefu modifying factors, according to Dan Kefuyin in Dan Kefu modifying factor collision probability definitions
The functional relation of son and equivalent one-dimensional rod moderator external diameter, equivalent one-dimensional rod moderator external diameter is obtained using binary chop method；
Equivalent one-dimensional rod problem is solved using subgroup method or ultra-fine group's method, obtain each circle of one-dimensional rod effectively shields section certainly.
To achieve these goals, it is practiced this invention takes following technical scheme：
A kind of Resonance self-shielding computational methods based on equivalent one-dimensional rod model for light water reactor, this method includes following step
Suddenly：
Step 1：Resonance self-shielding computational problem is that known materials composition and geological information solve having for fuel region resonance nucleic
Effect is from screen section, for light water reactor, and it is that black matrix i.e. absorption cross-section is infinitely great to make fuel region, and scattering section is zero, and source item is zero,
It is zero to make on-fuel area scattering section, and the value of absorption cross-section and source item is equal to elastic potential scattering section, and solution is transported using multigroup
Device solves below equation and obtains neutron angular flux：
Wherein Ω is angle,It is locus,It is angular flux,It is total cross section,It is elastic potential scattering
Section；The neutron scalar flux of each fuel rod is obtained using formula (2)：
Wherein i is the numbering of fuel rod, φiIt is the scalar flux of i-th fuel rod；
Step 2：For each fuel rod, it is that fuel rod is placed in into spatially infinity to build the isolated rod model of correspondence
In moderator, it is that black matrix i.e. absorption cross-section is infinitely great to make fuel region, and scattering section is zero, and source item is zero, the scattering of on-fuel area
Section is zero, and the value of absorption cross-section and source item is equal to elastic potential scattering section, and solution formula (1) obtains neutron angular flux, utilizes
Formula (2) calculates and obtains neutron scalar flux；
Step 3：The Dan Kefu modifying factors for obtaining each fuel rod are calculated using formula (3)：
Wherein CiIt is the Dan Kefu modifying factors of i-th fuel rod, φi,1And φi,2It is that step one and step 2 are obtained respectively
The scalar flux of i-th fuel rod arrived；
Step 4：The resonance of the corresponding equivalent one-dimensional rod of each fuel rod is built certainly according to Dan Kefu modifying factor conservations
Shield computational problem, equivalent one-dimensional rod material composition and fuel rod radius and fuel rod it is consistent, equivalent one-dimensional is solved below
The moderator external diameter of rod, Dan Kefu modifying factors and the functional relation such as formula (4) of equivalent one-dimensional rod moderator external diameter are shown：
Wherein CiIt is the Dan Kefu modifying factors for i-th fuel rod that step 3 is obtained, R is one-dimensional rod moderator external diameter,
PE, iIt is the neutron escape probability of i-th isolated rod of fuel rod correspondence, Pmf(R) it is fuel region is produced in one-dimensional rod neutron at it
The probability of initial collision, Σ occur in his regiontfIt is the total cross section of fuel region, it is infinity to make it, and l is the mean chord of fuel region
It is long, the corresponding equivalent one-dimensional rod moderator external diameter of i-th fuel rod is obtained using binary chop method according to formula (4), so far
The material composition and geological information of equivalent one-dimensional rod are obtained；
Step 5：The Resonance self-shielding of the equivalent one-dimensional rod obtained using subgroup method or ultra-fine group's method solution procedure 4 is calculated
Problem, the resonant nucleus for obtaining all each circles of equivalent one-dimensional rod have effect from screen section, and the resonant nucleus of equivalent one-dimensional rod have effect
Effect is have from screen section from the resonant nucleus that screen section is correspondence fuel rod in light water reactor, so far completes the Resonance self-shielding of light water reactor
Calculate.
Compared with prior art, the present invention has following outstanding advantages：
The present invention is using using the Dan Kefu modifying factors that fuel rod is calculated using neutron current method, and all resonance energy groups are only
Need to use a Dan Kefu modifying factor, it is only necessary to which once the simple group of full heap transports calculating, computational efficiency is higher；Utilize multigroup
Transporting solver and calculate neutron current, Dan Kefu modifying factors can be obtained in the case where there is complex geometry；Using subgroup side
Method or ultra-fine group's method calculate equivalent one-dimensional rod, and can obtain space correlation effectively shields each circle of section, i.e. fuel rod certainly
Effectively from screen section.
Brief description of the drawings
Fig. 1 is the equivalent process schematic diagram of one-dimensional rod.
Fig. 2 is fuel assembly.
Embodiment
The present invention is described in further detail with reference to the accompanying drawings and detailed description：
The present invention solves Dan Kefu modifying factors using neutron current method, according to the definition of Dan Kefu modifying factors neutron current and
The equivalence that collision probability is defined, the moderator external diameter of equivalent one-dimensional rod is obtained by binary chop method, finally using subgroup
Method or ultra-fine group's method solve the Resonance self-shielding computational problem of equivalent one-dimensional rod, and obtain space correlation effectively shields section certainly.
The specific calculation process of this method includes following aspect：
1) Resonance self-shielding computational problem be known materials composition and geological information solve fuel region resonance nucleic effectively from
Shield section, for the Resonance self-shielding computational problem of light water reactor, it is that (absorption cross-section is infinitely great, scattering section to black matrix to make fuel region
It is zero, source item is that zero), on-fuel area scattering section is zero, the value of absorption cross-section and source item is equal to elastic potential scattering section, uses
Multigroup transports solver solution formula (1) and obtains neutron angular flux；Due to the section of infinity can not possibly be taken in numerical computations,
Therefore typically it is taken as 1E5barn；Obtain after neutron angular flux, angular flux is integrated using formula (2), each is obtained
The neutron scalar flux of fuel rod；
2) for each fuel rod, the isolated rod model of correspondence is built, i.e., fuel rod is placed in the slow of spatially infinity
In agent, the external diameter that moderator is typically taken in numerical computations is 10cm, and boundary condition is vacuum boundary；It is black matrix to make fuel region,
I.e. absorption cross-section is 1E5barn, and scattering section is zero, and source item is zero, and on-fuel area scattering section is zero, absorption cross-section and source item
Value be equal to elastic potential scattering section, solution formula (1) obtains neutron angular flux, is calculated using formula (2) and obtains neutron mark and lead to
Amount；
3) the Dan Kefu modifying factors of each fuel rod are calculated using formula (3)；
4) because the neutron current of Dan Kefu modifying factors is defined, to be defined with collision probability be of equal value, therefore the pellet of fuel rod
Can husband's factor flux can with formula (4) represent, the external diameter of equivalent one-dimensional rod moderator can be obtained by binary chop method；
As shown in figure 1, the corresponding equivalent one-dimensional rod of a fuel rod in grid is obtained by above-mentioned steps, its material composition and fuel
The radius of rod fuel rod corresponding with grid it is consistent, the external diameter of moderator is obtained by above-mentioned calculating；
5) the Resonance self-shielding computational problem of equivalent one-dimensional rod is solved using subgroup method or ultra-fine group's method, equivalent one is obtained
Tie up effective screen section certainly of the space correlation of rod；Method, subgroup method and the ultra-fine group's method that the present invention is respectively adopted calculate Fig. 2
Shown component, the calculating time is 18s, 426s and 775s respectively, compared to subgroup method and ultra-fine group's method, side of the invention
Method has higher computational efficiency.
Claims (1)
1. a kind of Resonance self-shielding computational methods based on equivalent one-dimensional rod model for light water reactor, it is characterised in that：This method
Comprise the following steps：
Step 1：Resonance self-shielding computational problem be known materials composition and geological information solve fuel region resonance nucleic effectively from
Shield section, for light water reactor, it is that black matrix i.e. absorption cross-section is infinitely great to make fuel region, and scattering section is zero, and source item is zero, makes non-
Fuel region scattering section is zero, and the value of absorption cross-section and source item is equal to elastic potential scattering section, transports solver using multigroup and asks
Solution below equation obtains neutron angular flux：
Wherein Ω is angle,It is locus,It is angular flux,It is total cross section,It is elastic potential scattering section；
The neutron scalar flux of each fuel rod is obtained using formula (2)：
Wherein i is the numbering of fuel rod, φiIt is the scalar flux of i-th fuel rod；
Step 2：For each fuel rod, it is that fuel rod is placed in spatially infinitely great slowing down to build the isolated rod model of correspondence
In agent, it is that black matrix i.e. absorption cross-section is infinitely great to make fuel region, and scattering section is zero, and source item is zero, on-fuel area scattering section
It is zero, the value of absorption cross-section and source item is equal to elastic potential scattering section, and solution formula (1) obtains neutron angular flux, utilizes formula
(2) calculate and obtain neutron scalar flux；
Step 3：The Dan Kefu modifying factors for obtaining each fuel rod are calculated using formula (3)：
Wherein CiIt is the Dan Kefu modifying factors of i-th fuel rod, φi,1And φi,2Be respectively step one and step 2 obtain
The scalar flux of i root fuel rods；
Step 4：The Resonance self-shielding meter of the corresponding equivalent one-dimensional rod of each fuel rod is built according to Dan Kefu modifying factor conservations
Consistent, the solution equivalent one-dimensional rod below of calculation problem, the material composition of equivalent one-dimensional rod and the radius of fuel rod and fuel rod
Moderator external diameter, Dan Kefu modifying factors and the functional relation such as formula (4) of equivalent one-dimensional rod moderator external diameter are shown：
Wherein CiIt is the Dan Kefu modifying factors for i-th fuel rod that step 3 is obtained, R is one-dimensional rod moderator external diameter, Pe,iIt is
The neutron escape probability of the isolated rod of i roots fuel rod correspondence, Pmf(R) it is fuel region is produced in one-dimensional rod neutron in other regions
Occur the probability of initial collision, ΣtfIt is the total cross section of fuel region, it is infinity to make it,It is the mean chord of fuel region, according to
Formula (4) obtains the corresponding equivalent one-dimensional rod moderator external diameter of i-th fuel rod using binary chop method, has so far obtained
Imitate the material composition and geological information of one-dimensional rod；
Step 5：The Resonance self-shielding of the equivalent one-dimensional rod obtained using subgroup method or ultra-fine group's method solution procedure 4 is calculated and asked
Inscribe, the resonant nucleus for obtaining all each circles of equivalent one-dimensional rod have effect from screen section, and the resonant nucleus of equivalent one-dimensional rod have effect certainly
Screen section is that the resonant nucleus of correspondence fuel rod in light water reactor have effect from screen section, so far completes the Resonance self-shielding meter of light water reactor
Calculate.
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| CN110705054A (en) * | 2019-09-19 | 2020-01-17 | 西安交通大学 | Method for obtaining resonance group constant for neutron strong absorber |
| CN111914463A (en) * | 2020-08-12 | 2020-11-10 | 中国核动力研究设计院 | Subgroup optimization method and system for reactor assembly resonance simulation |
| CN111914464A (en) * | 2020-08-12 | 2020-11-10 | 中国核动力研究设计院 | Method and system for optimizing multi-resonance nuclide resonance simulation subgroup of reactor assembly |
| CN112364555A (en) * | 2020-11-19 | 2021-02-12 | 中国核动力研究设计院 | Dual-heterogeneity space self-screening effect correction method, device, equipment and medium |
| CN114491907A (en) * | 2020-10-27 | 2022-05-13 | 中国核动力研究设计院 | Resonance algorithm combining optimal rational polynomial and superfine group based on vacuum boundary |
| CN114510861A (en) * | 2022-04-19 | 2022-05-17 | 西安交通大学 | Resonance calculation method for studying reactor based on equivalent geometric theory |
| CN114692062A (en) * | 2022-03-31 | 2022-07-01 | 西安交通大学 | Method for efficiently obtaining nuclear reactor fuel rod surface partial neutron flux discontinuous factors |
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| CN110705054B (en) * | 2019-09-19 | 2021-06-11 | 西安交通大学 | Method for obtaining resonance group constant for neutron strong absorber |
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| CN111914463A (en) * | 2020-08-12 | 2020-11-10 | 中国核动力研究设计院 | Subgroup optimization method and system for reactor assembly resonance simulation |
| CN111914464A (en) * | 2020-08-12 | 2020-11-10 | 中国核动力研究设计院 | Method and system for optimizing multi-resonance nuclide resonance simulation subgroup of reactor assembly |
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| CN111914464B (en) * | 2020-08-12 | 2022-04-08 | 中国核动力研究设计院 | Method and system for optimizing multi-resonance nuclide resonance simulation subgroup of reactor assembly |
| CN114491907A (en) * | 2020-10-27 | 2022-05-13 | 中国核动力研究设计院 | Resonance algorithm combining optimal rational polynomial and superfine group based on vacuum boundary |
| CN114491907B (en) * | 2020-10-27 | 2023-10-20 | 中国核动力研究设计院 | Optimal rational polynomial and ultra-fine group combined resonance algorithm based on vacuum boundary |
| CN112364555B (en) * | 2020-11-19 | 2022-03-25 | 中国核动力研究设计院 | Dual-heterogeneity space self-screening effect correction method, device, equipment and medium |
| CN112364555A (en) * | 2020-11-19 | 2021-02-12 | 中国核动力研究设计院 | Dual-heterogeneity space self-screening effect correction method, device, equipment and medium |
| CN114692062A (en) * | 2022-03-31 | 2022-07-01 | 西安交通大学 | Method for efficiently obtaining nuclear reactor fuel rod surface partial neutron flux discontinuous factors |
| CN114692062B (en) * | 2022-03-31 | 2024-04-09 | 西安交通大学 | Method for efficiently obtaining partial neutron flow discontinuity factors on surface of nuclear reactor fuel rod |
| CN114510861A (en) * | 2022-04-19 | 2022-05-17 | 西安交通大学 | Resonance calculation method for studying reactor based on equivalent geometric theory |
| CN114510861B (en) * | 2022-04-19 | 2022-07-15 | 西安交通大学 | Resonance calculation method for studying reactor based on equivalent geometric theory |
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