CN108062987A - Reactor source item shielding analysis method and system - Google Patents
Reactor source item shielding analysis method and system Download PDFInfo
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- CN108062987A CN108062987A CN201610987540.2A CN201610987540A CN108062987A CN 108062987 A CN108062987 A CN 108062987A CN 201610987540 A CN201610987540 A CN 201610987540A CN 108062987 A CN108062987 A CN 108062987A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
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- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06Q—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES; SYSTEMS OR METHODS SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES, NOT OTHERWISE PROVIDED FOR
- G06Q10/00—Administration; Management
- G06Q10/06—Resources, workflows, human or project management; Enterprise or organisation planning; Enterprise or organisation modelling
- G06Q10/063—Operations research, analysis or management
- G06Q10/0631—Resource planning, allocation, distributing or scheduling for enterprises or organisations
- G06Q10/06313—Resource planning in a project environment
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- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06Q—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES; SYSTEMS OR METHODS SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES, NOT OTHERWISE PROVIDED FOR
- G06Q50/00—Systems or methods specially adapted for specific business sectors, e.g. utilities or tourism
- G06Q50/06—Electricity, gas or water supply
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
The present invention proposes that a kind of reactor source item shielding analysis method and system, this method comprise the following steps：A1：Target three-dimensional fuel component is chosen from the fuel assembly for be arranged in reactor core；A2：Obtain the material information of target three-dimensional fuel component；A3：The nucleic information of respective material is obtained according to material information, and the computation model of reactor core source item is obtained according to nucleic information；A4：It according to computation model, obtains nucleic information and changes with time information, and store nucleic information and change with time information.The present invention can realize that the automation of modeling with becoming more meticulous, improves the shield analysis precision of reactor, and can realize the Sources term analysis to single subassembly.
Description
Technical field
The present invention relates to reactor design field, more particularly to a kind of reactor source item shielding analysis method and it is
System.
Background technology
Reactor core is made of radioactive substance in nuclear power plant, and the water in primary Ioops and secondary circuit takes away the mistake of heat
It will also result in radioactive transfer in journey, it is therefore desirable to the radioactivity and its shield analysis in nuclear power plant are carried out, to ensure operation people
The safety of member.
The source item shield analysis of reactor, includes the source item and shield analysis of multiple systems in power plant, such as reactor core source item,
The contents such as primary Ioops source item, secondary circuit source item, reactor main shield, primary shielding, secondary shield.Reactor core source item is mainly used for point
Analysis fuel Radionuclide changes with time, and conventional method is using the average fuel combustion information of heap in-core as the defeated of reactor core source item
Enter condition, cause analysis precision not high, and the Sources term analysis of each fuel assembly can not be carried out respectively.SHIELDING CALCULATION is also base
It is estimated in the average data of reactor core, there has been no finely to the practice scheme of reactor core main shield Exact calculation in engineering at present.
The content of the invention
It is contemplated that at least solve one of above-mentioned technical problem.
For this purpose, an object of the present invention is to provide a kind of reactor source item shielding analysis method, this method can be real
The automation now modeled improves the shield analysis precision of reactor, and can realize to single subassembly with becoming more meticulous
Sources term analysis.
It is another object of the present invention to propose a kind of reactor source item shield analysis system.
To achieve these goals, the embodiment of first aspect present invention proposes a kind of reactor source item shield analysis side
Method comprises the following steps：A1：Target three-dimensional fuel component is chosen from the fuel assembly for being arranged in the reactor core；A2：
Obtain the material information of the target three-dimensional fuel component；A3：The nucleic information of respective material is obtained according to the material information,
And the computation model of reactor core source item is obtained according to the nucleic information；A4：According to the computation model, the nucleic information is obtained
Change with time information, and stores the nucleic information and change with time information.
Reactor source item shielding analysis method according to embodiments of the present invention, it is right based on three-dimensional micromodule information trace technology
The details of three-dimensional micromodule are calculated into line trace and applied to reactor source item shield analysis, realize the automation of modeling with
It becomes more meticulous, so as to improve the shield analysis precision of reactor；By the use of pre-stored three-dimensional fuel module information as source item,
The input condition of SHIELDING CALCULATION, so as to fulfill the Sources term analysis to single subassembly and fine SHIELDING CALCULATION.
In addition, reactor source item shielding analysis method according to the above embodiment of the present invention can also be with following additional
Technical characteristic：
In some instances, further include：B1：The reactor is built from reactor core to external geometrical model；B2：Obtain institute
State the three-dimensional information of three-dimensional fuel component in reactor；B3：According to the three-dimensional information of the three-dimensional fuel component and the geometry
Model obtains the computation model of the reactor main shield analysis；B4：The computation model analyzed according to the reactor main shield
Obtain neutron outside the reactor main shield and photon space and Energy distribution result.
In some instances, the step A2, further comprises：It is obtained from the three-dimensional micromodule information storage file to prestore
The material information of the target three-dimensional fuel component.
In some instances, the material information of the target three-dimensional fuel component includes：Title material and material axially divide
Area's information.
In some instances, in the step A3, according to the material information, from the three-dimensional micromodule information to prestore
The nucleic information of respective material is obtained in storage file.
In some instances, the step A4, further comprises：According to the computation model, by calling Sources term analysis
Program calculates the nucleic information situation of changing with time of the material, to obtain the change of the nucleic information at any time
Change information.
In some instances, the step B1, further comprises：According to the actual arrangement information of the reactor, structure
Geometrical model of the reactor from reactor core to out-pile.
In some instances, geometrical model of the reactor from reactor core to out-pile includes：Heap in-core three-dimensional fuel component
Arrangement, in-pile component, hanging basket, heat shielding, pressure vessel, heap external shielding layer.
In some instances, the step B2, further comprises：It is obtained from the three-dimensional micromodule information storage file to prestore
The three-dimensional information of the three-dimensional fuel component.
In some instances, the three-dimensional information of the three-dimensional fuel component includes：The burnup information and nucleon of fuel rod are close
Spend information.
In some instances, the step B4, further comprises：By calling shield analysis program, to the reactor
The computation model of main shield analysis carries out numerical computations, to obtain neutron outside the reactor main shield and photon space and energy
Measure distribution results.
In some instances, the three-dimensional micromodule information storage file to prestore includes the geometry of all three-dimensional fuel components
Information, material information, density of material, nucleic information and component arrangement information.
To achieve these goals, the embodiment of second aspect of the present invention proposes a kind of reactor source item shield analysis system
System, including：Module is chosen, the selection module is used to choose target three from the fuel assembly for being arranged in the reactor core
Tie up fuel assembly；First acquisition module, first acquisition module are used to obtain the material letter of the target three-dimensional fuel component
Breath；First modeling module, first modeling module are used to obtain the nucleic information of respective material according to the material information, and
The computation model of reactor core source item is obtained according to the nucleic information；First computing module, first computing module are used for basis
The computation model obtains the nucleic information and changes with time information, and stores the nucleic information and change with time
Information.
Reactor source item shield analysis system according to embodiments of the present invention is right based on three-dimensional micromodule information trace technology
The details of three-dimensional micromodule are calculated into line trace and applied to reactor source item shield analysis, realize the automation of modeling with
It becomes more meticulous, so as to improve the shield analysis precision of reactor；By the use of pre-stored three-dimensional fuel module information as source item,
The input condition of SHIELDING CALCULATION, so as to fulfill the Sources term analysis to single subassembly and fine SHIELDING CALCULATION.
In addition, reactor source item shield analysis system according to the above embodiment of the present invention can also be with following additional
Technical characteristic：
In some instances, further include：Second modeling module, second modeling module for build the reactor from
Reactor core is to external geometrical model；Second acquisition module, second acquisition module fire for obtaining three-dimensional in the reactor
Expect the three-dimensional information of component；3rd modeling module, the 3rd modeling module are used for the three-dimensional according to the three-dimensional fuel component
Information and the geometrical model obtain the computation model of the reactor main shield analysis；Second computing module, second meter
Module is calculated to be used to obtain the neutron and light outside the reactor main shield according to the computation model that the reactor main shield is analyzed
Subspace and Energy distribution result.
In some instances, first acquisition module is used for：It is obtained from the three-dimensional micromodule information storage file to prestore
The material information of the target three-dimensional fuel component.
In some instances, the material information of the target three-dimensional fuel component includes：Title material and material axially divide
Area's information.
In some instances, first modeling module is used for：According to the material information, from the three-dimensional group to prestore
The nucleic information of respective material is obtained in part information storage file.
In some instances, first computing module is used for：According to the computation model, by calling Sources term analysis journey
The nucleic information situation of changing with time of material described in ordered pair is calculated, and is changed with time with obtaining the nucleic information
Information.
In some instances, second modeling module is used for：According to the actual arrangement information of the reactor, institute is built
State geometrical model of the reactor from reactor core to out-pile.
In some instances, geometrical model of the reactor from reactor core to out-pile includes：Heap in-core three-dimensional fuel component
Arrangement, in-pile component, hanging basket, heat shielding, pressure vessel, heap external shielding layer.
In some instances, second acquisition module is used for：It is obtained from the three-dimensional micromodule information storage file to prestore
The three-dimensional information of the three-dimensional fuel component.
In some instances, the three-dimensional information of the three-dimensional fuel component includes：The burnup information and nucleon of fuel rod are close
Spend information.
In some instances, second computing module is used for：By calling shield analysis program, to the reactor master
The computation model of shield analysis carries out numerical computations, to obtain neutron outside the reactor main shield and photon space and energy
Distribution results.
In some instances, the three-dimensional micromodule information storage file to prestore includes the geometry of all three-dimensional fuel components
Information, material information, density of material, nucleic information and component arrangement information.
The additional aspect and advantage of the present invention will be set forth in part in the description, and will partly become from the following description
It obtains substantially or is recognized by the practice of the present invention.
Description of the drawings
The above-mentioned and/or additional aspect and advantage of the present invention will become in the description from combination accompanying drawings below to embodiment
Substantially and it is readily appreciated that, wherein：
Fig. 1 is the flow chart of reactor source item shielding analysis method according to embodiments of the present invention；
Fig. 2 is the flow diagram of reactor source item shielding analysis method in accordance with another embodiment of the present invention；
Fig. 3 is reactor main shield analysis process figure according to an embodiment of the invention；
Fig. 4 is the flow diagram of reactor main shield analysis in accordance with another embodiment of the present invention；
Fig. 5 is the structure diagram of reactor source item shield analysis system according to embodiments of the present invention；And
Fig. 6 is the structure diagram of reactor source item shield analysis system in accordance with another embodiment of the present invention.
Specific embodiment
The embodiment of the present invention is described below in detail, the example of the embodiment is shown in the drawings, wherein from beginning to end
Same or similar label represents same or similar element or has the function of same or like element.Below with reference to attached
The embodiment of figure description is exemplary, and is only used for explaining the present invention, and is not considered as limiting the invention.
In the description of the present invention, it is to be understood that term " " center ", " longitudinal direction ", " transverse direction ", " on ", " under ",
The orientation or position relationship of the instructions such as "front", "rear", "left", "right", " vertical ", " level ", " top ", " bottom ", " interior ", " outer " are
Based on orientation shown in the drawings or position relationship, it is for only for ease of the description present invention and simplifies description rather than instruction or dark
Show that signified device or element there must be specific orientation, with specific azimuth configuration and operation, thus it is it is not intended that right
The limitation of the present invention.In addition, term " first ", " second " are only used for description purpose, and it is not intended that instruction or hint are opposite
Importance.
In the description of the present invention, it is necessary to illustrate, unless otherwise clearly defined and limited, term " installation ", " phase
Even ", " connection " should be interpreted broadly, for example, it may be being fixedly connected or being detachably connected or be integrally connected；It can
To be mechanical connection or be electrically connected；It can be directly connected, can also be indirectly connected by intermediary, Ke Yishi
Connection inside two elements.For the ordinary skill in the art, with concrete condition above-mentioned term can be understood at this
Concrete meaning in invention.
Reactor source item shielding analysis method according to embodiments of the present invention and system are described below in conjunction with attached drawing.
Fig. 1 is the flow chart of reactor source item shielding analysis method according to an embodiment of the invention.Fig. 2 is according to this
Invent the flow diagram of the reactor source item shielding analysis method of another embodiment.As shown in Figure 1, and with reference to Fig. 2, according to
The reactor source item shielding analysis method of the embodiment of the present invention, comprises the following steps：
Step A1：Target three-dimensional fuel component is chosen from the fuel assembly for be arranged in reactor core.In other words namely
It chooses and is arranged in a certain box fuel assembly of reactor core, using as target three-dimensional fuel component.
Step A2：Obtain the material information of target three-dimensional fuel component.
In one embodiment of the invention, step A2 further comprises：From the three-dimensional micromodule information storage file to prestore
The middle material information for obtaining target three-dimensional fuel component.Wherein, the material information of target three-dimensional fuel component for example including：Material
Title and material axial direction partition information etc..Wherein, the above-mentioned three-dimensional micromodule information storage file to prestore is for example by a kind of reaction
Heap three-dimensional micromodule information trace technology generates, and geological information, material information, material including all three-dimensional fuel components are close
Degree, nucleic information and component arrangement information etc., the information of these storages is also the basis of the present invention.
Step A3：The nucleic information of respective material is obtained according to material information, and reactor core source item is obtained according to nucleic information
Computation model.
Specifically, in step A3, according to material information, obtain and correspond to from the three-dimensional micromodule information storage file to prestore
The nucleic information of material.Wherein, the above-mentioned three-dimensional micromodule information storage file to prestore is for example by a kind of reactor three-dimensional micromodule
Information trace technology generates, geological information, material information including all three-dimensional fuel components, density of material, nucleic information
And component arrangement information etc..In other words, i.e., for each material, the reading pair from the three-dimensional micromodule information storage file to prestore
The nucleic information of material is answered, for the modeling of reactor core source item, so as to obtain the computation model of reactor core source item.
Step A4：According to computation model, obtain nucleic information and change with time information, and store nucleic information at any time
Change information.
In one embodiment of the invention, step A4 further comprises：According to the calculating of reactor core source item obtained above
Model, by the way that Sources term analysis program is called to calculate the nucleic information situation of changing with time of the material, to obtain core
Prime information changes with time information, and further result of calculation is stored.
In other words, i.e. above-mentioned steps A1 to A5 describes the process to reactor core Sources term analysis.Further, for next box
The reactor core Sources term analysis process of fuel assembly (choosing next target three-dimensional fuel component again), repeats step A1 extremely
A4.
In one embodiment of the invention, with reference to shown in Fig. 3 and Fig. 4, this method is further comprising the steps of：
Step B1：Reactor is built from reactor core to external geometrical model.The step, that is, reactor main shield analysis geometry
Modeling process.
In one embodiment of the invention, step B1 further comprises：According to the actual arrangement information of reactor, structure
Build geometrical model of the reactor from reactor core to out-pile.Wherein, geometrical model of the reactor from reactor core to out-pile for example including：Reactor core
The contents such as interior three-dimensional fuel component arrangement, in-pile component, hanging basket, heat shielding, pressure vessel, heap external shielding layer.
Step B2：Obtain the three-dimensional information of three-dimensional fuel component in reactor.
In one embodiment of the invention, step B2 further comprises：From the three-dimensional micromodule information storage file to prestore
The middle three-dimensional information for obtaining three-dimensional fuel component.More specifically, the three-dimensional information of three-dimensional fuel component for example including：Fuel rod
Burnup information and nucleon density information etc..Wherein, the above-mentioned three-dimensional micromodule information storage file to prestore is for example by a kind of anti-
Heap three-dimensional micromodule information trace technology is answered to generate, geological information, material information, material including all three-dimensional fuel components are close
Degree, nucleic information and component arrangement information etc..
Step B3：According to the three-dimensional information and geometrical model of three-dimensional fuel component, the meter of reactor main shield analysis is obtained
Calculate model.In other words, i.e., according to the information (the burnup information of such as fuel rod and nucleon density information) and step obtained in step B2
The reactor obtained in rapid B1 is from reactor core to external geometrical model, the computation model of structure reactor main shield analysis calculating.
Step B4：The computation model analyzed according to reactor main shield obtains neutron and photon sky outside reactor main shield
Between and Energy distribution result.
In one embodiment of the invention, step B4 further comprises：By calling shield analysis program, to step
Obtained in B3 reactor main shield analysis computation model carry out numerical computations, with obtain the neutron outside reactor main shield and
Photon space and Energy distribution result.
In other words, i.e. above-mentioned steps B1 to B5 describes the process to reactor main shield analysis.
To sum up, the reactor source item shielding analysis method of the embodiment of the present invention can realize the accurate Sources term analysis of reactor
With shield analysis.
Reactor source item shielding analysis method according to embodiments of the present invention, it is right based on three-dimensional micromodule information trace technology
The details of three-dimensional micromodule are calculated into line trace and applied to reactor source item shield analysis, realize the automation of modeling with
It becomes more meticulous, so as to improve the shield analysis precision of reactor；By the use of pre-stored three-dimensional fuel module information as source item,
The input condition of SHIELDING CALCULATION, so as to fulfill the Sources term analysis to single subassembly and fine SHIELDING CALCULATION.
Further embodiment of the present invention also proposed a kind of reactor source item shield analysis system.
Fig. 5 is the structure diagram of reactor source item shield analysis system according to an embodiment of the invention.Such as Fig. 5 institutes
Show, the reactor source item shield analysis system 100, including：Choose module 110, the first acquisition module 120, the first modeling module
130 and first computing module 140.
Wherein, module 110 is chosen to be used to choose target three-dimensional fuel group from the fuel assembly for be arranged in reactor core
Part.In other words namely choose and be arranged in a certain box fuel assembly of reactor core, using as target three-dimensional fuel component.
First acquisition module 120 is used to obtain the material information of target three-dimensional fuel component.
In one embodiment of the invention, the first acquisition module 120 is used for：Text is stored from the three-dimensional micromodule information to prestore
The material information of target three-dimensional fuel component is obtained in part.More specifically, the material information of target three-dimensional fuel component is for example
Including：Title material and material axial direction partition information etc..Wherein, the above-mentioned three-dimensional micromodule information storage file to prestore for example passes through
A kind of reactor three-dimensional micromodule information trace technology generation, geological information, material information including all three-dimensional fuel components,
Density of material, nucleic information and component arrangement information etc..
First modeling module 130 is used to obtain the nucleic information of respective material according to material information, and according to nucleic information
Obtain the computation model of reactor core source item.
In one embodiment of the invention, the first modeling module 130 is used for：According to material information, from the three-dimensional to prestore
The nucleic information of respective material is obtained in module information storage file.Wherein, the above-mentioned three-dimensional micromodule information storage file to prestore
Such as generated by a kind of reactor three-dimensional micromodule information trace technology, the geological information including all three-dimensional fuel components,
Material information, density of material, nucleic information and component arrangement information etc..In other words, i.e., for each material, from three to prestore
The nucleic information that respective material is read in module information storage file is tieed up, for the modeling of reactor core source item, so as to obtain reactor core
The computation model of source item.
First computing module 140 is used for according to computation model, is obtained nucleic information and is changed with time information, and stores core
Prime information changes with time information.
In one embodiment of the invention, the first computing module 140 is used for：According to the meter of reactor core source item obtained above
Model is calculated, by the way that Sources term analysis program is called to calculate the nucleic information situation of changing with time of material, to obtain core
Prime information changes with time information, and further result of calculation is stored.
In one embodiment of the invention, with reference to shown in Fig. 6, which further includes：Second modeling module 150,
Two acquisition modules 160, the 3rd modeling module 170 and the second computing module 180.
Wherein, the second modeling module 150 is used to build reactor from reactor core to external geometrical model.
In one embodiment of the invention, the second modeling module 150 is used for：According to the actual arrangement information of reactor,
Build geometrical model of the reactor from reactor core to out-pile.Wherein, geometrical model of the reactor from reactor core to out-pile for example including：Heap
The contents such as the arrangement of in-core three-dimensional fuel component, in-pile component, hanging basket, heat shielding, pressure vessel, heap external shielding layer.
Second acquisition module 160 is used to obtain the three-dimensional information of three-dimensional fuel component in reactor.
In one embodiment of the invention, the second acquisition module 160 is used for：Text is stored from the three-dimensional micromodule information to prestore
The three-dimensional information of three-dimensional fuel component is obtained in part.More specifically, the three-dimensional information of three-dimensional fuel component for example including：Fuel
Burnup information and nucleon density information of stick etc..Wherein, the above-mentioned three-dimensional micromodule information storage file to prestore for example passes through one kind
Reactor three-dimensional micromodule information trace technology generates, and includes geological information, material information, the material of all three-dimensional fuel components
Density, nucleic information and component arrangement information etc..
3rd modeling module 170 is used for three-dimensional information and geometrical model according to three-dimensional fuel component, obtains reactor master
The computation model of shield analysis.In other words, i.e., according to the burnup information of fuel rod obtained above and nucleon density information and
The reactor arrived is from reactor core to external geometrical model, the computation model of structure reactor main shield analysis calculating.
Second computing module 180 is used to be obtained outside reactor main shield according to the computation model that reactor main shield is analyzed
Neutron and photon space and Energy distribution result.
In one embodiment of the invention, the second computing module 180 is used for：By calling shield analysis program, to upper
The computation model for the reactor main shield analysis stated carries out numerical computations, to obtain the neutron and light outside reactor main shield
Subspace and Energy distribution result.
To sum up, the reactor source item shield analysis system of the embodiment of the present invention can realize the accurate Sources term analysis of reactor
With shield analysis.
It should be noted that the specific implementation of the reactor source item shield analysis system of the embodiment of the present invention and this hair
The specific implementation of the reactor source item shielding analysis method of bright embodiment is similar, specifically refers to the description of method part,
In order to reduce redundancy, details are not described herein again.
Reactor source item shield analysis system according to embodiments of the present invention is right based on three-dimensional micromodule information trace technology
The details of three-dimensional micromodule are calculated into line trace and applied to reactor source item shield analysis, realize the automation of modeling with
It becomes more meticulous, so as to improve the shield analysis precision of reactor；By the use of pre-stored three-dimensional fuel module information as source item,
The input condition of SHIELDING CALCULATION, so as to fulfill the Sources term analysis to single subassembly and fine SHIELDING CALCULATION.
In the description of this specification, reference term " one embodiment ", " some embodiments ", " example ", " specifically show
The description of example " or " some examples " etc. means specific features, structure, material or the spy for combining the embodiment or example description
Point is contained at least one embodiment of the present invention or example.In the present specification, schematic expression of the above terms is not
Centainly refer to identical embodiment or example.Moreover, particular features, structures, materials, or characteristics described can be any
One or more embodiments or example in combine in an appropriate manner.
Although an embodiment of the present invention has been shown and described, it will be understood by those skilled in the art that：Not
In the case of departing from the principle of the present invention and objective a variety of change, modification, replacement and modification can be carried out to these embodiments, this
The scope of invention is by claim and its equivalent limits.
Claims (24)
1. a kind of reactor source item shielding analysis method, which is characterized in that comprise the following steps：
A1：Target three-dimensional fuel component is chosen from the fuel assembly for being arranged in the reactor core；
A2：Obtain the material information of the target three-dimensional fuel component；
A3：The nucleic information of respective material is obtained according to the material information, and reactor core source item is obtained according to the nucleic information
Computation model；
A4：According to the computation model, obtain the nucleic information and change with time information, and store the nucleic information with
The change information of time.
2. reactor source item shielding analysis method according to claim 1, which is characterized in that further include：
B1：The reactor is built from reactor core to external geometrical model；
B2：Obtain the three-dimensional information of three-dimensional fuel component in the reactor；
B3：According to the three-dimensional information of the three-dimensional fuel component and the geometrical model, the reactor main shield analysis is obtained
Computation model；
B4：The computation model analyzed according to the reactor main shield obtains neutron and photon sky outside the reactor main shield
Between and Energy distribution result.
3. reactor source item shielding analysis method according to claim 1, which is characterized in that the step A2, further
Including：
The material information of the target three-dimensional fuel component is obtained from the three-dimensional micromodule information storage file to prestore.
4. the reactor source item shielding analysis method described in claim 3, which is characterized in that the target three-dimensional fuel component
Material information includes：Title material and material axial direction partition information.
5. the reactor source item shielding analysis method described in claim 4, which is characterized in that in the step A3, according to institute
Material information is stated, the nucleic information of respective material is obtained from the three-dimensional micromodule information storage file to prestore.
6. reactor source item shielding analysis method according to claim 1, which is characterized in that the step A4, further
Including：
According to the computation model, changed with time by calling Sources term analysis program to the nucleic information of the material situation
It is calculated, is changed with time information with obtaining the nucleic information.
7. reactor source item shielding analysis method according to claim 2, which is characterized in that the step B1, further
Including：
According to the actual arrangement information of the reactor, geometrical model of the reactor from reactor core to out-pile is built.
8. reactor source item shielding analysis method according to claim 7, which is characterized in that the reactor from reactor core to
The geometrical model of out-pile includes：The arrangement of heap in-core three-dimensional fuel component, in-pile component, hanging basket, heat shielding, pressure vessel, heap external screen
Cover layer.
9. reactor source item shielding analysis method according to claim 2, which is characterized in that the step B2, further
Including：
The three-dimensional information of the three-dimensional fuel component is obtained from the three-dimensional micromodule information storage file to prestore.
10. reactor source item shielding analysis method according to claim 9, which is characterized in that the three-dimensional fuel component
Three-dimensional information include：The burnup information of fuel rod and nucleon density information.
11. reactor source item shielding analysis method according to claim 2, which is characterized in that the step B4, further
Including：
By calling shield analysis program, numerical computations are carried out to the computation model of reactor main shield analysis, to obtain
Neutron and photon space and Energy distribution result outside the reactor main shield.
12. the reactor source item shielding analysis method according to claim 5 or 9, which is characterized in that the three-dimensional to prestore
Module information storage file includes geological information, material information, density of material, nucleic information and the group of all three-dimensional fuel components
Part arrangement information.
13. a kind of reactor source item shield analysis system, which is characterized in that including：
Module is chosen, the selection module is used to choose the three-dimensional combustion of target from the fuel assembly for being arranged in the reactor core
Expect component；
First acquisition module, first acquisition module are used to obtain the material information of the target three-dimensional fuel component；
First modeling module, first modeling module are used to obtain the nucleic information of respective material according to the material information,
And the computation model of reactor core source item is obtained according to the nucleic information；
First computing module, first computing module are used for according to the computation model, obtain the nucleic information at any time
Change information, and store the nucleic information and change with time information.
14. reactor source item shield analysis system according to claim 13, which is characterized in that further include：
Second modeling module, second modeling module are used to build the reactor from reactor core to external geometrical model；
Second acquisition module, second acquisition module are used to obtain the three-dimensional information of three-dimensional fuel component in the reactor；
3rd modeling module, the 3rd modeling module is for the three-dimensional information according to the three-dimensional fuel component and the geometry
Model obtains the computation model of the reactor main shield analysis；
Second computing module, second computing module are used to obtain institute according to the computation model that the reactor main shield is analyzed
State neutron outside reactor main shield and photon space and Energy distribution result.
15. reactor source item shield analysis system according to claim 13, which is characterized in that first acquisition module
For：
The material information of the target three-dimensional fuel component is obtained from the three-dimensional micromodule information storage file to prestore.
16. reactor source item shield analysis system according to claim 15, which is characterized in that the target three-dimensional fuel
The material information of component includes：Title material and material axial direction partition information.
17. reactor source item shield analysis system according to claim 16, which is characterized in that first modeling module
For：
According to the material information, the nucleic that respective material is obtained from the three-dimensional micromodule information storage file to prestore is believed
Breath.
18. reactor source item shield analysis system according to claim 13, which is characterized in that first computing module
For：
According to the computation model, changed with time by calling Sources term analysis program to the nucleic information of the material situation
It is calculated, is changed with time information with obtaining the nucleic information.
19. reactor source item shield analysis system according to claim 14, which is characterized in that second modeling module
For：
According to the actual arrangement information of the reactor, geometrical model of the reactor from reactor core to out-pile is built.
20. reactor source item shield analysis system according to claim 19, which is characterized in that the reactor is from reactor core
Geometrical model to out-pile includes：The arrangement of heap in-core three-dimensional fuel component, in-pile component, hanging basket, heat shielding, pressure vessel, out-pile
Shielded layer.
21. reactor source item shield analysis system according to claim 14, which is characterized in that second acquisition module
For：
The three-dimensional information of the three-dimensional fuel component is obtained from the three-dimensional micromodule information storage file to prestore.
22. reactor source item shield analysis system according to claim 21, which is characterized in that the three-dimensional fuel component
Three-dimensional information include：The burnup information of fuel rod and nucleon density information.
23. reactor source item shield analysis system according to claim 14, which is characterized in that second computing module
For：
By calling shield analysis program, numerical computations are carried out to the computation model of reactor main shield analysis, to obtain
Neutron and photon space and Energy distribution result outside the reactor main shield.
24. the reactor source item shield analysis system according to claim 17 or 21, which is characterized in that it is described prestore three
Tie up module information storage file include the geological informations of all three-dimensional fuel components, material information, density of material, nucleic information and
Component arrangement information.
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