CN114528719B - Online energy group compression method for pressurized water reactor based on two-dimensional reactor core - Google Patents

Online energy group compression method for pressurized water reactor based on two-dimensional reactor core Download PDF

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CN114528719B
CN114528719B CN202210425172.8A CN202210425172A CN114528719B CN 114528719 B CN114528719 B CN 114528719B CN 202210425172 A CN202210425172 A CN 202210425172A CN 114528719 B CN114528719 B CN 114528719B
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CN114528719A (en
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刘宙宇
周欣宇
吴宏春
曹良志
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Xian Jiaotong University
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Abstract

The invention discloses an online energy group compression method for a pressurized water reactor based on a two-dimensional reactor core, which comprises the steps of firstly, geometrically dividing a three-dimensional pressurized water reactor core to be simulated into a plurality of layers along the axial direction; establishing a resonance model and a transportation model of a fine group for each layer; solving the resonance model and the transport model of the thin cluster to obtain the neutron angular flux density of the thin cluster and the neutron standard flux density of the thin cluster of each flat source region; obtaining a wide group neutron cross section of the material based on the subgroup neutron angular flux density and the subgroup neutron nominal flux density of the flat source region and the subgroup neutron cross section of the material; and establishing a transport model of the three-dimensional pressurized water reactor based on the neutron cross section of the wide group, and solving to obtain the neutron angular flux density of the three-dimensional wide group and the neutron standard flux density of the thin group. The method can obtain the angular flux density and the standard flux density of the neutron in the thin group in the on-line radial reflecting layer area, the obtained neutron cross section of the wide group is more accurate, the solving precision is high, the method can be used for the rapid simulation calculation of a numerical reactor, and the unnecessary safety margin in the pressurized water reactor design is reduced.

Description

Online energy group compression method for pressurized water reactor based on two-dimensional reactor core
Technical Field
The invention relates to the field of nuclear reactor core design and safety, in particular to an online energy group compression method for a pressurized water reactor based on a two-dimensional reactor core.
Background
With the continuous development of the nuclear power industry, the high-fidelity numerical simulation method adopts the direct solution of the whole reactor core, reduces the approximate improvement of the design precision in the calculation method, thereby reducing the unnecessary safety margin in the pressurized water reactor, ensuring the safety of the pressurized water reactor and simultaneously improving the economy of the pressurized water reactor, and is an important technical development direction.
The high-fidelity numerical simulation method adopts the whole reactor core to directly solve, the number of calculated energy groups is large, and currently adopted energy group structures comprise a Helios-49 group, an AMPX-51 group, a WIMS-69 group and the like. The energy group structure has too many energy groups, which causes larger memory of numerical reactor calculation and lower calculation precision, and seriously restricts the engineering application of the high-fidelity numerical simulation method.
The existing energy group compression method mostly adopts an off-line method, which can not ensure the accuracy of the neutron cross section of the material, so that the accuracy of the high-fidelity numerical simulation pressurized water reactor is lower. In addition, the existing grid cell-based online energy group compression method cannot provide online neutron flux distribution in a pressurized water reactor reflecting layer area, so that the neutron section accuracy of a material in the pressurized water reactor reflecting layer area is low, and the further reduction of the number of wide group energy group structures is restricted.
Disclosure of Invention
In order to overcome the problems in the prior art, the invention provides an online energy group compression method for a pressurized water reactor based on a two-dimensional reactor core, which is characterized in that through resonance and transport simulation of a fine group on a two-dimensional reactor core plane layer, wide group neutron cross sections of materials in all regions of each two-dimensional reactor core plane layer of the pressurized water reactor are obtained online, a reactor core three-dimensional transport model is constructed based on the wide group neutron cross sections, and the three-dimensional wide group neutron angular flux density and neutron standard flux density of the reactor core are obtained through calculation.
In order to realize the purpose, the invention adopts the following technical scheme to implement:
an online energy group compression method for a pressurized water reactor based on a two-dimensional core comprises the following steps:
step 1: reading geometric information, material information, boundary condition information and energy cluster structure information of a thin cluster and a wide cluster of a pressurized water reactor three-dimensional reactor core to be simulated;
step 2: according to the geometric information and material information of the three-dimensional reactor core of the pressurized water reactor obtained in the step 1, the geometric information and the material information of the three-dimensional reactor core of the pressurized water reactor are obtained, the pressurized water reactor core is divided into a plurality of two-dimensional reactor core plane layers along the axial direction at the insertion depth position of a control rod and at the position where the axial material changes, a fine group neutron resonance model is established for each material area of each layer, as shown in a formula (1), a fine group neutron transport model of a grid of a flat source area is established for each material area of each layer, as shown in a formula (2);
Figure 539423DEST_PATH_IMAGE001
（1）
wherein the content of the first and second substances,
F-total number of fuel zones of a two-dimensional core planar layer of the pressurized water reactor;
M-total moderator zone count for a two-dimensional core planar layer of the pressurized water reactor;
Figure 945128DEST_PATH_IMAGE002
second of the two-dimensional core plane of the pressurized water reactorfuFuel zone ofgA total neutron cross-section of the cluster;
Figure 760637DEST_PATH_IMAGE003
second of the two-dimensional core plane of the pressurized water reactorfuFuel zone ofgNeutron flux density of the population;
Figure 438743DEST_PATH_IMAGE004
second of the two-dimensional core plane of the pressurized water reactorfuThe volume of the fuel zone;
Figure 483053DEST_PATH_IMAGE005
slave fuel region of a two-dimensional core planar layer of a pressurized water reactor
Figure 195795DEST_PATH_IMAGE006
Generation ofgGroup neutron in fuel areafuProbability of a first collision occurring;
Figure 182205DEST_PATH_IMAGE007
fuel region of two-dimensional core plane layer of pressurized water reactor
Figure 613186DEST_PATH_IMAGE006
(ii) a neutron source intensity of;
Figure 461188DEST_PATH_IMAGE008
second of the two-dimensional core plane of the pressurized water reactor
Figure 825173DEST_PATH_IMAGE006
The volume of the fuel zone;
Figure 716906DEST_PATH_IMAGE009
slave moderator zone of a two-dimensional core plane of a pressurized water reactormoGeneration ofgGroup neutron in fuel areafuProbability of a first collision occurring;
Figure 120336DEST_PATH_IMAGE010
moderator zone of a two-dimensional core plane layer of a pressurized water reactormo(ii) a neutron source intensity of;
Figure 21296DEST_PATH_IMAGE011
moderator zone of a two-dimensional core plane layer of a pressurized water reactormoThe volume of (a);
Figure 974209DEST_PATH_IMAGE012
（2）
wherein the content of the first and second substances,
i-flat source region numbering;
xof rectangular co-ordinate systemsxAxial coordinates;
yof rectangular co-ordinate systemsyAxial coordinates;
Figure 36843DEST_PATH_IMAGE013
-directionpAndxcosine value of the angle in the positive direction of the axis;
Figure 927569DEST_PATH_IMAGE014
-directionpAndycosine value of the angle in the positive direction of the axis;
Figure 366641DEST_PATH_IMAGE015
second of the two-dimensional core plane of the pressurized water reactoriFlat source region ofgEdge of groupp(ii) a directional subgroup neutron angular flux density;
Figure 908481DEST_PATH_IMAGE016
second of the two-dimensional core plane of the pressurized water reactoriFlat source region ofgThe total cross-section of the neutrons of the cluster,tis the neutron total cross section symbol;
Figure 407595DEST_PATH_IMAGE017
second of the two-dimensional core plane of the pressurized water reactoriFlat source region ofgThe neutron scattering cross-section of the cluster,sis a neutron scattering cross section symbol;
Figure 582356DEST_PATH_IMAGE018
second of the two-dimensional core plane of the pressurized water reactoriFlat source region ofgThe neutron fission cross-section of the cluster,fis a symbol of a neutron fission cross section,
Figure 559539DEST_PATH_IMAGE019
is the average number of neutrons per fission;
Figure 221465DEST_PATH_IMAGE020
second of the two-dimensional core plane of the pressurized water reactoriFlat source region ofgNeutron fluence in a fine population of populations;
Figure 642213DEST_PATH_IMAGE021
-a first steplThe characteristic value of the iteration step;
ω p -neutron angular flux density atpWeight in direction;
and step 3: acquiring the sub-cluster neutron angular flux density and the sub-cluster neutron standard flux density of the flat source area of each layer according to the sub-cluster neutron resonance model and the sub-cluster neutron transport model established in the step 2;
and 4, step 4: obtaining a wide group neutron cross section of the material of each layer by combining the thin group neutron cross section of each material of each layer according to the thin group neutron flux density and the thin group neutron standard flux density of the flat source region of each layer obtained in the step (3), as shown in a formula (3);
Figure 491220DEST_PATH_IMAGE022
（3）
wherein the content of the first and second substances,
Figure 334411DEST_PATH_IMAGE023
second of the two-dimensional core plane of the pressurized water reactoriA flat source region ofgNeutron fluence in a fine population of populations;
Figure 601576DEST_PATH_IMAGE024
second of the two-dimensional core plane of the pressurized water reactormA first materialgThe neutron cross-section of a fine population of the population,typeincluding total cross-section, scattering cross-section, fission cross-section;
Figure 442493DEST_PATH_IMAGE025
second of the two-dimensional core plane of the pressurized water reactormA first materialGThe cross-section of the neutrons in a wide cluster of clusters,typeincluding total cross-section, scattering cross-section, fission cross-section;
and 5: establishing a neutron transport model of the pressurized water reactor three-dimensional reactor core according to the wide group neutron cross section of each layer of material in the step 4, wherein the neutron transport model is shown in a formula (4);
Figure 778796DEST_PATH_IMAGE026
（4）
wherein the content of the first and second substances,
i-flat source region numbering;
xof rectangular co-ordinate systemsxAn axial direction;
yof rectangular co-ordinate systemsyAn axial direction;
zof rectangular co-ordinate systemszAn axial direction;
Figure 97782DEST_PATH_IMAGE027
-directionpAnd withxCosine value of the angle in the positive direction of the axis;
Figure 219453DEST_PATH_IMAGE028
-directionpAndycosine value of the angle in the positive direction of the axis;
Figure 231271DEST_PATH_IMAGE029
-directionpAndzcosine value of the angle in the positive direction of the axis;
Figure 320450DEST_PATH_IMAGE030
-neutron angular flux density atpWeight in direction;
Figure 443127DEST_PATH_IMAGE031
third dimension of core of pressurized water reactoriFlat source region ofGThe total cross-section of the neutrons in a wide cluster of clusters,tis the neutron total cross section symbol;
Figure 684883DEST_PATH_IMAGE032
third dimension of core of pressurized water reactoriFlat source region ofGThe wide cluster neutron scattering cross-section of the cluster,sis a neutron scattering cross section symbol;
Figure 133182DEST_PATH_IMAGE033
third dimension of core of pressurized water reactoriA flat source region ofGThe wide cluster neutron fission cross-section of the cluster,fis a symbol of a neutron fission cross section,
Figure 444078DEST_PATH_IMAGE034
is the average number of neutrons per fission;
Figure 370445DEST_PATH_IMAGE035
third dimension of core of pressurized water reactoriFlat source region ofGIn the direction of the grouppWide cluster neutron angular flux density;
Figure 466709DEST_PATH_IMAGE036
third dimension of core of pressurized water reactoriFlat source region ofGNeutron fluence in a wide population of populations;
Figure 820330DEST_PATH_IMAGE037
-a first steplThe characteristic value of the iteration step;
step 6: and (5) solving the neutron transport model of the pressurized water reactor three-dimensional reactor core in the step (5) to obtain the three-dimensional wide-cluster neutron angular flux density and the wide-cluster neutron standard flux density.
Compared with the prior art, the invention has the following outstanding advantages:
according to the method, based on resonance and transport simulation of thin clusters on a two-dimensional reactor core plane layer, wide cluster neutron cross sections of materials of all regions of each two-dimensional reactor core plane layer of the pressurized water reactor are obtained on line, a reactor core three-dimensional transport model is constructed based on the wide cluster neutron cross sections, and the three-dimensional wide cluster neutron angular flux density and neutron standard flux density of the reactor core are obtained through calculation. The method can be used for the rapid simulation calculation of the numerical reactor, reduces unnecessary safety margin in the pressurized water reactor design, improves the economy of the pressurized water reactor, and lays a foundation for the engineering application of the numerical reactor in the pressurized water reactor core design.
Drawings
FIG. 1 is a flow chart of the method of the present invention.
FIG. 2 is a schematic diagram of a computational object of a pressurized water reactor core.
Detailed Description
The present invention will be described in further detail with reference to the accompanying drawings and specific embodiments.
The specific steps of the method are shown in fig. 1, and fig. 2 shows a pressurized water reactor core, wherein the left side is the three-dimensional geometry of the pressurized water reactor core, and the right side is a plurality of two-dimensional core plane layer geometries which are split along the axial direction. The method comprises the steps of axially dividing a three-dimensional pressurized water reactor core to be simulated in FIG. 2 into a plurality of layers, establishing a fine group neutron resonance model for each material area of each layer, dividing a flat source area grid for each material area of each layer, and establishing a flat source area grid fine group neutron transport model; solving a thin cluster neutron resonance model and a thin cluster neutron transport model to obtain the thin cluster neutron angular flux density and the thin cluster neutron standard flux density of each flat source region; obtaining a wide group neutron cross section of the material based on the thin group neutron standard flux density of the flat source region and the thin group neutron cross section of the material; and establishing a neutron transport model of the three-dimensional pressurized water reactor based on the neutron cross section of the wide group, and solving to obtain the neutron angular flux density of the three-dimensional wide group and the neutron standard flux density of the wide group. The method comprises the following specific steps:
step 1: reading geometric information, material information, boundary condition information and energy cluster structure information of a thin cluster and a wide cluster of a pressurized water reactor three-dimensional reactor core to be simulated;
step 2: according to the geometric information and material information of the three-dimensional reactor core of the pressurized water reactor obtained in the step 1, at the insertion depth position of a control rod and the position where the axial material changes, the pressurized water reactor core is geometrically and axially divided into a plurality of two-dimensional reactor core plane layers, a fine group neutron resonance model is established for each material area of each layer, as shown in a formula (1), a flat source area grid is divided for each material area of each layer, and a fine group neutron transport model of the flat source area grid is established, as shown in a formula (2);
Figure 348580DEST_PATH_IMAGE039
（1）
wherein the content of the first and second substances,
F-total number of fuel zones of a two-dimensional core planar layer of the pressurized water reactor;
M-total moderator zone count for a two-dimensional core planar layer of the pressurized water reactor;
Figure 299349DEST_PATH_IMAGE040
second of the two-dimensional core plane of the pressurized water reactorfuFuel zone ofgA total neutron cross-section of the cluster;
Figure 823872DEST_PATH_IMAGE041
second of the two-dimensional core plane of the pressurized water reactorfuFuel zone ofgNeutron flux density of the population;
Figure 109360DEST_PATH_IMAGE042
second of the two-dimensional core plane of the pressurized water reactorfuThe volume of the fuel zone;
Figure 643109DEST_PATH_IMAGE043
slave fuel region of a two-dimensional core planar layer of a pressurized water reactor
Figure 448385DEST_PATH_IMAGE044
To produce the firstgGroup neutron in fuel areafuProbability of a first collision occurring;
Figure 143809DEST_PATH_IMAGE045
fuel region of two-dimensional core plane layer of pressurized water reactor
Figure 916593DEST_PATH_IMAGE044
(ii) a neutron source intensity of;
Figure 988454DEST_PATH_IMAGE046
second of the two-dimensional core plane of the pressurized water reactor
Figure 100766DEST_PATH_IMAGE044
The volume of the fuel zone;
Figure 803578DEST_PATH_IMAGE047
slave moderator zone of a two-dimensional core plane of a pressurized water reactormoGeneration ofgGroup neutron in fuel areafuProbability of a first collision occurring;
Figure 798079DEST_PATH_IMAGE048
moderator zone of a two-dimensional core plane layer of a pressurized water reactormo(ii) a neutron source intensity of;
Figure 673631DEST_PATH_IMAGE049
moderator zone of a two-dimensional core plane layer of a pressurized water reactormoThe volume of (a);
Figure 187920DEST_PATH_IMAGE050
（2）
wherein the content of the first and second substances,
i-flat source region number;
xof rectangular co-ordinate systemsxAn axial coordinate;
yof rectangular co-ordinate systemsyAxial coordinates;
Figure 490725DEST_PATH_IMAGE051
-directionpAndxcosine of the angle in the positive direction of the axis;
Figure 175785DEST_PATH_IMAGE052
-directionpAndycosine value of the angle in the positive direction of the axis;
Figure 589448DEST_PATH_IMAGE053
second of the two-dimensional core plane of the pressurized water reactoriFlat source region ofgEdge of groupp(ii) a directional subgroup neutron angular flux density;
Figure 473091DEST_PATH_IMAGE054
second of the two-dimensional core plane of the pressurized water reactoriA flat source region ofgThe total cross-section of the neutrons of the cluster,tis the neutron total cross section symbol;
Figure 697530DEST_PATH_IMAGE055
second of the two-dimensional core plane of the pressurized water reactoriFlat source region ofgThe neutron scattering cross-section of the cluster,sis a neutron scattering cross section symbol;
Figure 666623DEST_PATH_IMAGE056
second of the two-dimensional core plane of the pressurized water reactoriFlat source region ofgThe neutron fission cross-section of the cluster,fis a symbol of a neutron fission cross section,
Figure 883978DEST_PATH_IMAGE057
is the average number of neutrons per fission;
Figure 622127DEST_PATH_IMAGE058
second of two-dimensional core plane layer of pressurized water reactoriFlat source region ofgNeutron fluence in a fine population of populations;
Figure 17467DEST_PATH_IMAGE059
-a first steplThe characteristic value of the iteration step;
ω p neutron angular flux density atpWeight in direction;
and step 3: acquiring the sub-cluster neutron angular flux density and the sub-cluster neutron standard flux density of the flat source area of each layer according to the sub-cluster neutron resonance model and the sub-cluster neutron transport model established in the step 2;
and 4, step 4: obtaining a wide group neutron cross section of the material of each layer by combining the thin group neutron cross section of each material of each layer according to the thin group neutron flux density and the thin group neutron standard flux density of the flat source region of each layer obtained in the step (3), as shown in a formula (3);
Figure 473856DEST_PATH_IMAGE060
（3）
wherein the content of the first and second substances,
Figure 494902DEST_PATH_IMAGE061
second of the two-dimensional core plane of the pressurized water reactoriA flat source region ofgNeutron fluence in a fine population of populations;
Figure 353136DEST_PATH_IMAGE062
second of the two-dimensional core plane of the pressurized water reactormA first materialgThe neutron cross-section of a fine population of the population,typeincluding total cross-section, scattering cross-section, fission cross-section;
Figure 653799DEST_PATH_IMAGE063
second of two-dimensional core plane layer of pressurized water reactormA first materialGThe cross-section of the neutrons in a wide cluster of clusters,typeincluding total cross-section, scattering cross-section, fission cross-section;
and 5: establishing a neutron transport model of the pressurized water reactor three-dimensional reactor core according to the wide group neutron cross section of each layer of material in the step 4, wherein the neutron transport model is shown in a formula (4);
Figure 597484DEST_PATH_IMAGE026
（4）
wherein the content of the first and second substances,
i-flat source region numbering;
xof rectangular co-ordinate systemsxAn axial direction;
yof rectangular coordinatesyAn axial direction;
zof rectangular co-ordinate systemszAn axial direction;
Figure 156641DEST_PATH_IMAGE064
-directionpAndxcosine value of the angle in the positive direction of the axis;
Figure 869382DEST_PATH_IMAGE065
-directionpAndycosine value of the angle in the positive direction of the axis;
Figure 606525DEST_PATH_IMAGE066
-directionpAndzcosine value of the angle in the positive direction of the axis;
Figure 303086DEST_PATH_IMAGE067
-neutron angular flux density atpWeight in direction;
Figure 59077DEST_PATH_IMAGE068
third dimension of core of pressurized water reactoriFlat source region ofGThe total cross-section of the neutrons in a wide cluster of clusters,tis the neutron total cross section symbol;
Figure 691571DEST_PATH_IMAGE069
third dimension of core of pressurized water reactoriA flat source region ofGThe wide cluster neutron scattering cross-section of the cluster,sis a neutron scattering cross section symbol;
Figure 68457DEST_PATH_IMAGE070
third dimension of core of pressurized water reactoriFlat source region ofGThe wide cluster neutron fission cross-section of the cluster,fis a symbol of a neutron fission cross section,
Figure 799784DEST_PATH_IMAGE071
is the average number of neutrons per fission;
Figure 513793DEST_PATH_IMAGE072
third dimension of core of pressurized water reactoriPingyuanZone ofGIn the direction of the grouppWide cluster neutron angular flux density;
Figure 810913DEST_PATH_IMAGE073
third dimension of core of pressurized water reactoriFlat source region ofGNeutron fluence in a wide population of populations;
Figure 587460DEST_PATH_IMAGE074
-a first steplThe characteristic value of the iteration step;
step 6: and (5) solving the neutron transport model of the pressurized water reactor three-dimensional reactor core in the step (5) to obtain the three-dimensional wide-cluster neutron angular flux density and the wide-cluster neutron standard flux density.

Claims (1)

1. An online energy group compression method for a pressurized water reactor based on a two-dimensional reactor core is characterized by comprising the following steps: the method comprises the following steps:
step 1: reading geometric information, material information, boundary condition information and energy cluster structure information of a thin cluster and a wide cluster of a pressurized water reactor three-dimensional reactor core to be simulated;
step 2: according to the geometric information and material information of the three-dimensional reactor core of the pressurized water reactor obtained in the step 1, the geometric information and the material information of the three-dimensional reactor core of the pressurized water reactor are obtained, the pressurized water reactor core is divided into a plurality of two-dimensional reactor core plane layers along the axial direction at the insertion depth position of a control rod and at the position where the axial material changes, a fine group neutron resonance model is established for each material area of each layer, as shown in a formula (1), a fine group neutron transport model of a grid of a flat source area is established for each material area of each layer, as shown in a formula (2);
Figure 466401DEST_PATH_IMAGE001
（1）
wherein the content of the first and second substances,
F-total number of fuel zones of a two-dimensional core planar layer of the pressurized water reactor;
Mtwo-dimensional pressurized water reactorTotal moderator zone count for the core planar layer;
Figure 295817DEST_PATH_IMAGE002
second of the two-dimensional core plane of the pressurized water reactorfuFuel zone ofgA total neutron cross-section of the cluster;
Figure 666624DEST_PATH_IMAGE003
second of the two-dimensional core plane of the pressurized water reactorfuFuel zone ofgNeutron flux density of the population;
Figure 770846DEST_PATH_IMAGE004
second of the two-dimensional core plane of the pressurized water reactorfuThe volume of the fuel zone;
Figure 130283DEST_PATH_IMAGE005
slave fuel region of two-dimensional core plane layer of pressurized water reactor
Figure 661759DEST_PATH_IMAGE006
Generation ofgGroup neutron in fuel areafuProbability of a first collision occurring;
Figure 5015DEST_PATH_IMAGE007
fuel region of two-dimensional core plane layer of pressurized water reactor
Figure 647349DEST_PATH_IMAGE006
(ii) a neutron source intensity of;
Figure 644649DEST_PATH_IMAGE008
second of two-dimensional core plane layer of pressurized water reactor
Figure 347026DEST_PATH_IMAGE009
The volume of the fuel zone;
Figure 177578DEST_PATH_IMAGE010
slave moderator zone of a two-dimensional core plane layer of a pressurized water reactormoTo produce the firstgGroup neutron in fuel areafuProbability of a first collision occurring;
Figure 358024DEST_PATH_IMAGE011
moderator zone of a two-dimensional core plane layer of a pressurized water reactormo(ii) a neutron source intensity of;
Figure 957632DEST_PATH_IMAGE012
moderator zone of a two-dimensional core plane layer of a pressurized water reactormoThe volume of (a);
Figure 830911DEST_PATH_IMAGE013
（2）
wherein the content of the first and second substances,
i-flat source region numbering;
xof rectangular co-ordinate systemsxAxial coordinates;
yof rectangular co-ordinate systemsyAn axial coordinate;
Figure 148759DEST_PATH_IMAGE014
-directionpAndxcosine value of the angle in the positive direction of the axis;
Figure 116584DEST_PATH_IMAGE015
-directionpAnd withyCosine value of the angle in the positive direction of the axis;
Figure 836279DEST_PATH_IMAGE016
second of the two-dimensional core plane of the pressurized water reactoriFlat source region ofgEdge of groupp(ii) a directional subgroup neutron angular flux density;
Figure 880458DEST_PATH_IMAGE017
second of the two-dimensional core plane of the pressurized water reactoriFlat source region ofgThe total cross-section of the neutrons of the cluster,tis the neutron total cross section symbol;
Figure 685603DEST_PATH_IMAGE018
second of the two-dimensional core plane of the pressurized water reactoriFlat source region ofgThe neutron scattering cross-section of the cluster,sis a neutron scattering cross section symbol;
Figure 473430DEST_PATH_IMAGE019
second of the two-dimensional core plane of the pressurized water reactoriFlat source region ofgThe neutron fission cross-section of the cluster,fis a symbol of a neutron fission cross section,
Figure 47631DEST_PATH_IMAGE020
is the average number of neutrons per fission;
Figure 246400DEST_PATH_IMAGE021
second of the two-dimensional core plane of the pressurized water reactoriFlat source region ofgNeutron fluence in a fine population of populations;
Figure 273262DEST_PATH_IMAGE022
-a first steplCharacteristic values of the iteration steps;
ω p -neutronsAngular flux density ofpA weight in a direction;
and step 3: acquiring the sub-cluster neutron angular flux density and the sub-cluster neutron standard flux density of the flat source area of each layer according to the sub-cluster neutron resonance model and the sub-cluster neutron transport model established in the step 2;
and 4, step 4: obtaining a wide group neutron cross section of the material of each layer by combining the thin group neutron cross section of each material of each layer according to the thin group neutron flux density and the thin group neutron standard flux density of the flat source region of each layer obtained in the step (3), as shown in a formula (3);
Figure 864780DEST_PATH_IMAGE023
（3）
wherein the content of the first and second substances,
Figure 293488DEST_PATH_IMAGE024
second of two-dimensional core plane layer of pressurized water reactoriA flat source region ofgNeutron fluence in a fine population of populations;
Figure 679470DEST_PATH_IMAGE025
second of two-dimensional core plane layer of pressurized water reactormA first materialgThe neutron cross-section of a fine population of the population,typeincluding total cross-section, scattering cross-section, fission cross-section;
Figure 193628DEST_PATH_IMAGE026
second of the two-dimensional core plane of the pressurized water reactormA first materialGThe cross-section of the neutrons in a wide cluster of clusters,typeincluding total cross-section, scattering cross-section, fission cross-section;
and 5: establishing a neutron transport model of the pressurized water reactor three-dimensional reactor core according to the wide group neutron cross section of each layer of material in the step 4, wherein the neutron transport model is shown in a formula (4);
Figure 323258DEST_PATH_IMAGE027
（4）
wherein the content of the first and second substances,
i-flat source region numbering;
xof rectangular co-ordinate systemsxAn axial direction;
yof rectangular co-ordinate systemsyAn axial direction;
zof rectangular co-ordinate systemszAn axial direction;
Figure 855739DEST_PATH_IMAGE028
-directionpAndxcosine value of the angle in the positive direction of the axis;
Figure 678202DEST_PATH_IMAGE029
-directionpAndycosine value of the angle in the positive direction of the axis;
Figure 679656DEST_PATH_IMAGE030
-directionpAndzcosine value of the angle in the positive direction of the axis;
Figure 612977DEST_PATH_IMAGE031
neutron angular flux density atpWeight in direction;
Figure 750697DEST_PATH_IMAGE032
third dimension of core of pressurized water reactoriFlat source region ofGThe total cross-section of the neutrons in a wide cluster of clusters,tis the neutron total cross section symbol;
Figure 478481DEST_PATH_IMAGE033
of three-dimensional core of pressurized water reactorFirst, theiFlat source region ofGThe wide cluster neutron scattering cross-section of the cluster,sis a neutron scattering cross section symbol;
Figure 967232DEST_PATH_IMAGE034
third dimension of core of pressurized water reactoriFlat source region ofGThe wide cluster neutron fission cross-section of the cluster,fis a symbol of a neutron fission cross section,
Figure 690861DEST_PATH_IMAGE035
is the average number of neutrons per fission;
Figure 948667DEST_PATH_IMAGE036
third dimension of core of pressurized water reactoriFlat source region ofGIn the direction of the grouppWide cluster neutron angular flux density;
Figure 112933DEST_PATH_IMAGE037
third dimension of core of pressurized water reactoriFlat source region ofGNeutron fluence in a wide population of populations;
Figure 557820DEST_PATH_IMAGE038
-a first steplThe characteristic value of the iteration step;
step 6: and (5) solving the neutron transport model of the pressurized water reactor three-dimensional reactor core in the step (5) to obtain the three-dimensional wide-cluster neutron angular flux density and the wide-cluster neutron standard flux density.
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