CN107391904A - A kind of fusion reactor tritium breeds covering Optimization Design - Google Patents
A kind of fusion reactor tritium breeds covering Optimization Design Download PDFInfo
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- CN107391904A CN107391904A CN201710451767.XA CN201710451767A CN107391904A CN 107391904 A CN107391904 A CN 107391904A CN 201710451767 A CN201710451767 A CN 201710451767A CN 107391904 A CN107391904 A CN 107391904A
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- G16—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR SPECIFIC APPLICATION FIELDS
- G16C—COMPUTATIONAL CHEMISTRY; CHEMOINFORMATICS; COMPUTATIONAL MATERIALS SCIENCE
- G16C10/00—Computational theoretical chemistry, i.e. ICT specially adapted for theoretical aspects of quantum chemistry, molecular mechanics, molecular dynamics or the like
Abstract
The invention discloses a kind of fusion reactor tritium to breed covering Optimization Design, including neutronics, thermohydraulics and structure optimization three big procedure modules of analysis.In the iteration optimization starting stage of neutronics thermohydraulics, full pile neutron credit analysis only provides the neutron wall load being applied on the first wall, Neutronics analysis based on one-dimensional cylinder model obtains TBR and deposited with the nuclear heat needed for thermohydraulics analysis, and nuclear heat deposition is normalized into neutron wall load, establishes two-dimentional radial arrangement thermohydraulics computation model.After the radial arrangement of covering meets neutronics and thermohydraulics requirement simultaneously, resettle complete cladding structure and carry out full pile neutron, thermohydraulics and structure mechanics analysis, finally determine optimal cladding structure.Neutronics can be avoided using this method and thermohydraulics iterates the complicated Geometric Modeling process being related in optimization process, improve the optimization design efficiency of fusion reactor tritium propagation covering.
Description
Technical field
The present invention relates to fusion reactor blanket field, specifically a kind of fusion reactor tritium propagation covering Optimization Design.
Background technology
Fusion reactor tritium propagation covering is the core component around plasma, is the core technology load that fusion energy moves towards application
Body, major function include propagation tritium to realize the self-holding nuclear fusion reaction of deuterium-tritium；It is available by the energy conversion of Fusion Neutron
Heat, while take heat out of generating；Shielding neutron prevents from polluting environment.By years of researches, domestic and international fusion circle exists
Best of breed is found in structural material, multiplication agent and cooling agent three, develops a variety of covering concepts, including low operational factor
Covering（450 ~ 500 DEG C of coolant outlet temperature）To the high parameter covering with high attraction（Coolant outlet temperature 600 ~
1000℃）.Classify by cooling agent, fusion reactor tritium propagation covering concept can be divided into：（1）The cold ceramics of helium/liquid multiplication agent covering is general
Read；（2）Water cooling ceramics/liquid multiplication agent covering concept；（3）Liquid multiplication agent（Such as LiPb）Self-cooled blanket concept.
Tritium propagation blanket design is the process of a multiple-objection optimization, from neutronics, the angle of thermohydraulics and structure
Degree sees that the specific requirement that optimal covering should be able to meet includes：Tritium breeding ratio（TBR）>1, material temperature is less than limit value, breeding blanket
Mean temperature releasing in tritium temperature range, cooling agent operational factor meets design criteria, and cladding structure in normal and thing
Therefore intensity requirement can be met under operating mode.Existing design method step is as follows：（1）It is primarily based on the covering three of original hypothesis
Tie up structure and carry out Neutronics analysis, obtain the significant data such as TBR and nuclear heat deposition, structure is corrected according to the TBR of feedback,
Calculating iterate until TBR meets to require；（2）The nuclear heat deposition and cladding structure obtained according to Neutronics analysis, establishes heat
Work hydraulics analysis model, and carry out thermohydraulics analysis, if being as a result unsatisfactory for requiring, need repeat step（1）, weight
New adjustment cladding structure；（3）After the requirement for meeting neutronics-thermohydraulics at the same time, and then carry out structural stress analysis, such as
Fruit does not reach requirement, then needs to make to adjust structure, return to step（1）Restart to calculate analysis.Covering optimization design relates to
And multiple iterative calculation, the analysis of each step all include the work of complicated 3 d geometric modeling process, especially neutronics modeling
Work amount is very big, modeled components include heap in all tritiums propagation covering, divertor, Shield blanket, magnetic induction loop, superconducting magnet and
Vacuum vessel port etc..Therefore, for raising operating efficiency, the Optimization Design for studying covering is significant.
At present, the Optimization Design of the tritium propagation covering of document report is less.The U.S. carries from the angle of Neutronics analysis
A kind of high efficiency method for calculating fusion reactor Shield blanket nuclear heat deposition, the knot that result of calculation obtains with three-dimensional neutronics model are gone out
Fruit is consistent, and the optimization design for breeding covering to tritium has reference function.Its method is that complete three-dimensional mask covering is placed on into one
In the part for tieing up cylinder neutronics model, reflecting layer is used to border in the ring of model and pole, in being applied on covering
Sub- wall load is obtained by detailed three-dimensional Neutronics analysis, and important parameter includes neutron flux, energy and angle distribution.This method is kept away
Exempt from the establishment of full pile neutron model, improve computational efficiency, but the deficiency being applied in tritium propagation covering optimization design
Be in：（1）Need to establish complete geometry, workload is still very big, and this is unfavorable for iterating for tritium propagation covering
Design；（2）The analysis method of thermal-hydraulic and structure is not extended to, can not determine whether clad material temperature and stress surpass
Mark, the feedback regulation to tritium propagation covering optimization have little significance；（3）The nuclear heat for stressing to calculate structural material deposits, and can not obtain
TBR values.
The content of the invention is existing to solve it is an object of the invention to provide a kind of fusion reactor tritium propagation covering Optimization Design
There is workload existing for the Optimization Design of technology fusion reactor tritium propagation covering big, it is impossible to determine whether material temperature is exceeded,
The problem of tritium breeds covering TBR values can not truly be reflected.
In order to achieve the above object, the technical solution adopted in the present invention is：
A kind of fusion reactor tritium breeds covering Optimization Design, it is characterised in that：Comprise the following steps：
（1）, obtain the neutron wall load being applied on the wall surface of covering first based on full fusion reactor Neutronics analysis, neutron wall carries
Lotus normalizes to Fusion power；
（2）, the three-dimensional structure of covering is simplified to radial arrangement, and correspond in one-dimensional cylinder neutronics model, use is one-dimensional
Cylinder neutronics model does Neutronics analysis and calculates the required nuclear heat deposition of thermohydraulics analysis and TBR, by what is calculated
Nuclear heat is deposited and TBR normalizes to neutron wall load, and radial arrangement is adjusted according to the TBR of feedback, until TBR meets to want
Ask；
（3）, based on the radial arrangement optimized, establish thermohydraulics analysis model, and carry out thermohydraulics analysis, if
Material temperature is exceeded, then return to step（2）Radial arrangement is adjusted, nuclear heat deposition and TBR are recalculated, until meeting heat
The requirement of work hydraulics；
（4）, on the basis of the radial arrangement optimized, complete three-dimensional cladding structure is established, according to the dimensioning of fusion reactor
It is very little to establish complete neutronics model, and detailed cladding structure is internally created, nuclear heat deposition and TBR are calculated, carries out heat
Work hydraulics and structure credit analysis, if TBR, material temperature and structural stress are unsatisfactory for requiring, then return to step（1）Again change
Generation optimization.
A kind of described fusion reactor tritium propagation covering Optimization Design, it is characterised in that：The step（2）In, consider
To the geometry of Tokamak Fusion Reactor, Neutronics analysis is done using one-dimensional cylinder neutronics model, obtains TBR and thermal technology's water
Nuclear heat deposition needed for mechanical analysis, surrounding layer and inner cladding radially have identical arrangement, and wherein radial arrangement is according to covering
Actual three-dimensional structure is simplified, and every layer of lattice cell is made up of uniform material, during the nuclear heat calculated deposition is normalized to
Sub- wall load.
A kind of described fusion reactor tritium propagation covering Optimization Design, it is characterised in that：The step（3）In, thermal technology
Hydraulics analysis model using simplified two-dimentional radial arrangement, according to the cladding structure of reality come true by the type of flow of cooling agent
It is fixed.
A kind of described fusion reactor tritium propagation covering Optimization Design, it is characterised in that：Step in whole process（1）、
（2）Form Neutronics analysis procedure module, step（3）Form thermohydraulics analysis procedure module, step（4）Form structure
Optimization analysis procedure module；Realized respectively in Neutronics analysis, thermohydraulics analysis and structure optimization analysis procedure module
Coupling iterative calculation, neutronics, thermohydraulics and structure optimization program are after the convergence of each procedure module inner iteration, its result
Next procedure module is fed back to, carries out next procedure module iteration successively.
The present invention proposes a kind of new tritium propagation covering Optimization Design, breeds available for various types of tritiums and wraps
Design of the layer in terms of neutronics and thermohydraulics.The program not only avoids cumbersome 3 d geometric modeling in iteration optimization
Process, operating efficiency is improved, and cladding structure can be bred to tritium according to the material temperature of feedback, structural stress and TBR
It is adjusted, can be quickly met the optimal tritium propagation covering of neutronics-thermohydraulics-structure requirement simultaneously.
It is of the invention with existing fusion reactor tritium breed covering Optimization Design compared with, its advantage is：
1. in the starting stage of neutronics iteration optimization design, computation model uses one-dimensional cylinder, and the nuclear heat deposition calculated is returned
One changes and arrive neutron wall load, and compared with full pile neutron, this method not only avoid complicated Geometric Modeling process, and can be with
Nuclear heat similar in acquisition deposits, and improves operating efficiency.
2. thermohydraulics and structure mechanics analysis have been extended to, and in the initial of thermohydraulics iteration optimization design
In the stage, computation model is using the radial arrangement of two dimension, and compared with the cladding structure of three-dimensional, this method can obtain similar temperature
Field distribution, while the Geometric Modeling process of complexity is avoided, it can expeditiously determine to meet the radial arrangement that thermal technology requires.
3. TBR value can be efficiently obtained in iteration optimization, the structure of covering is adjusted according to the value, progressively
Approach optimal cladding structure.
Brief description of the drawings
Fig. 1 is the flow chart of the present invention.
Fig. 2 is the one-dimensional cylinder model schematic diagram of the present invention.
Embodiment
As shown in figure 1, a kind of Optimization Design of fusion reactor tritium propagation covering, it includes neutronics, thermohydraulics
Optimize three big procedure modules of analysis with structure, it is as follows the step of this method：（1）Full heap is established according to the physical dimension of fusion reactor
Model 1, carry out full pile neutron credit analysis 2-1 and obtain the neutron wall load being applied on the wall surface of covering first, neutron wall load
Normalize to Fusion power；（2）The three-dimensional structure of covering is simplified to radial arrangement, and corresponds to one-dimensional cylinder neutronics model
In, carry out Neutronics analysis 3-1, the nuclear heat calculated deposition and TBR are normalized into neutron wall load, according to the TBR of feedback
Radial arrangement 6 is adjusted, until TBR meets to require；（3）Based on radial arrangement, carry out thermohydraulics analysis 4-1, if material
Temperature exceeding standard, then return to step（2）Radial arrangement is adjusted, nuclear heat deposition and TBR are recalculated, until meeting thermal technology's water
Mechanical requirements；（4）On the basis of the radial arrangement optimized, complete three-dimensional cladding structure is established, in full pile neutron mould
Detailed cladding structure is created in type, carries out full pile neutron credit analysis 2-2, calculates nuclear heat deposition and TBR, carry out thermal-hydraulic
4-2 and structural analysis 5 are analysed in credit, if TBR, material temperature and structural stress are unsatisfactory for requiring, then adjust cladding structure 7 and return
Step（1）Again iteration optimization.
In the starting stage of neutronics iteration optimization analysis, using one-dimensional cylinder model, because the model and tokamak
The geometry of fusion reactor has preferable similitude, as shown in Figure 2.According to the actual three-dimensional structure of fusion reactor blanket, by covering
It is reduced to radially arranged multilayer lattice cell, it is assumed that material uniformly mixes in each lattice cell.The model is divided into by plasma chamber 8
The radial arrangement 9 of surrounding layer and inner cladding region, wherein surrounding layer and the radial arrangement 10 of inner cladding are identical, and primary structure all wraps
Include breeding blanket 11, Neutron multiplication agent 12, the first wall 13, coldplate 14 and backboard 15.In the analysis of thermohydraulics iteration optimization
Starting stage, computation model are simplified two dimensional model, and on the basis of radial arrangement, the connected mode of coldplate 14 is according to reality
The cladding structure on border determines.
The part that the present invention does not state in detail, belongs to techniques well known.
Although the illustrative embodiment of the present invention is described above content, in order to the technology of this area
Personnel understand the present invention.It should be apparent that the invention is not restricted to the scope of embodiment, to the common skill of the art
For art personnel, if various change appended claim and present invention determine that spirit and scope in, these changes are
It will be apparent that in the row of protection of the invention.
Claims (4)
1. a kind of fusion reactor tritium breeds covering Optimization Design, it is characterised in that：Comprise the following steps：
（1）, obtain the neutron wall load being applied on the wall surface of covering first based on full fusion reactor Neutronics analysis, neutron wall carries
Lotus normalizes to Fusion power；
（2）, the three-dimensional structure of covering is simplified to radial arrangement, and correspond in one-dimensional cylinder neutronics model, use is one-dimensional
Cylinder neutronics model does Neutronics analysis and calculates the required nuclear heat deposition of thermohydraulics analysis and TBR, by what is calculated
Nuclear heat is deposited and TBR normalizes to neutron wall load, and radial arrangement is adjusted according to the TBR of feedback, until TBR meets to want
Ask；
（3）, based on the radial arrangement optimized, establish thermohydraulics analysis model, and carry out thermohydraulics analysis, if
Material temperature is exceeded, then return to step（2）Radial arrangement is adjusted, nuclear heat deposition and TBR are recalculated, until meeting heat
The requirement of work hydraulics；
（4）, on the basis of the radial arrangement optimized, complete three-dimensional cladding structure is established, according to the dimensioning of fusion reactor
It is very little to establish complete neutronics model, and detailed cladding structure is internally created, nuclear heat deposition and TBR are calculated, carries out heat
Work hydraulics and structure credit analysis, if TBR, material temperature and structural stress are unsatisfactory for requiring, then return to step（1）Again change
Generation optimization.
A kind of 2. fusion reactor tritium propagation covering Optimization Design according to claim 1, it is characterised in that：The step
（2）In, it is contemplated that the geometry of Tokamak Fusion Reactor, Neutronics analysis is done using one-dimensional cylinder neutronics model, obtained
TBR and thermohydraulics analyze required nuclear heat deposition, and surrounding layer and inner cladding radially have identical arrangement, wherein radial direction cloth
Put and simplified according to the actual three-dimensional structure of covering, every layer of lattice cell is made up of uniform material, and the nuclear heat calculated is deposited
Normalize to neutron wall load.
A kind of 3. fusion reactor tritium propagation covering Optimization Design according to claim 1, it is characterised in that：The step
（3）In, thermohydraulics analysis model is using simplified two-dimentional radial arrangement, and the type of flow of cooling agent is according to actual covering
Structure determines.
A kind of 4. fusion reactor tritium propagation covering Optimization Design according to claim 1, it is characterised in that：Whole process
Middle step（1）、（2）Form Neutronics analysis procedure module, step（3）Form thermohydraulics analysis procedure module, step（4）
Form structure optimization analysis procedure module；Neutronics analysis, thermohydraulics analysis and structure optimization analysis procedure module
Middle to realize coupling iterative calculation respectively, neutronics, thermohydraulics and structure optimization program are received in each procedure module inner iteration
After holding back, its result feeds back to next procedure module, carries out next procedure module iteration successively.
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Cited By (5)
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| CN110148478A (en) * | 2019-06-10 | 2019-08-20 | 中国科学院合肥物质科学研究院 | A kind of fusion reactor solid-state water cooling covering production tritium multiplication agent-neutron multiplication agent |
| CN110569613A (en) * | 2019-09-12 | 2019-12-13 | 西安交通大学 | Method applied to fusion reactor cladding accurate engineering design |
| CN112597711A (en) * | 2020-12-21 | 2021-04-02 | 西安交通大学 | Nuclear thermo-fluid-solid coupling analysis method applied to fusion reactor cladding |
| CN113836683A (en) * | 2020-06-08 | 2021-12-24 | 核工业西南物理研究院 | Intelligent acceleration method for improving breeding ratio of tritium produced by fusion reactor to tritium blanket |
| CN114611267A (en) * | 2021-12-03 | 2022-06-10 | 中国核动力研究设计院 | Abnormal tritium permeation analysis method, system, terminal and medium in neutron irradiation environment |
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Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110148478A (en) * | 2019-06-10 | 2019-08-20 | 中国科学院合肥物质科学研究院 | A kind of fusion reactor solid-state water cooling covering production tritium multiplication agent-neutron multiplication agent |
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| CN113836683A (en) * | 2020-06-08 | 2021-12-24 | 核工业西南物理研究院 | Intelligent acceleration method for improving breeding ratio of tritium produced by fusion reactor to tritium blanket |
| CN113836683B (en) * | 2020-06-08 | 2023-08-15 | 核工业西南物理研究院 | Intelligent acceleration method for improving tritium proliferation ratio of tritium-producing cladding of fusion reactor |
| CN112597711A (en) * | 2020-12-21 | 2021-04-02 | 西安交通大学 | Nuclear thermo-fluid-solid coupling analysis method applied to fusion reactor cladding |
| CN112597711B (en) * | 2020-12-21 | 2022-12-09 | 西安交通大学 | Nuclear thermo-fluid-solid coupling analysis method applied to fusion reactor cladding |
| CN114611267A (en) * | 2021-12-03 | 2022-06-10 | 中国核动力研究设计院 | Abnormal tritium permeation analysis method, system, terminal and medium in neutron irradiation environment |
| CN114611267B (en) * | 2021-12-03 | 2023-09-12 | 中国核动力研究设计院 | Abnormal tritium permeation analysis method, system, terminal and medium in neutron irradiation environment |
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Application publication date: 20171124 |