CN102663151A - Nuclear radiation shielding material optimization design method - Google Patents

Nuclear radiation shielding material optimization design method Download PDF

Info

Publication number
CN102663151A
CN102663151A CN2012100542519A CN201210054251A CN102663151A CN 102663151 A CN102663151 A CN 102663151A CN 2012100542519 A CN2012100542519 A CN 2012100542519A CN 201210054251 A CN201210054251 A CN 201210054251A CN 102663151 A CN102663151 A CN 102663151A
Authority
CN
China
Prior art keywords
nuclear radiation
optimization
genetic algorithm
radiation shield
designing
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Granted
Application number
CN2012100542519A
Other languages
Chinese (zh)
Other versions
CN102663151B (en
Inventor
胡华四
张天奎
郭威
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Xian Jiaotong University
Original Assignee
Xian Jiaotong University
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Xian Jiaotong University filed Critical Xian Jiaotong University
Priority to CN201210054251.9A priority Critical patent/CN102663151B/en
Publication of CN102663151A publication Critical patent/CN102663151A/en
Application granted granted Critical
Publication of CN102663151B publication Critical patent/CN102663151B/en
Expired - Fee Related legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Landscapes

  • Compositions Of Macromolecular Compounds (AREA)

Abstract

The present invention discloses a nuclear radiation shielding material optimization design method, comprising the following steps: (1) initializing a material ratio; (2) according to the element ratio obtained in step (1), respectively calculating physical quantities of shielding properties, thermal properties, mechanical properties and etc. of characteristic materials; (3) making results of step (2) dimensionless and then calculating a weighted sum; (4) obtaining an optimized objective function value from step (3), the value being one daughter of genetic algorithm; corresponding to the material ratio adaptation characteristics, using the genetic algorithm to conduct choosing, crossing and variation to give a new material component ratio, and then repeating step (1); outputting an optimized material ratio after the objective function gets an optimum value through loop calculation. The nuclear radiation shielding material optimization design method, 1) realizes component optimization design of a plurality of materials, 2) can be easily complied to a computer program for improving searching efficiency and effectively guiding the design and production of a nuclear radiation shielding material, and 3) comprehensively takes multiple properties of materials into account, and thus is capable of optimizing and designing a novel shielding material with good comprehensive properties.

Description

A kind of nuclear radiation shield optimization of material method for designing
Technical field:
The invention belongs to field of materials, relate to a kind of optimization of material method for designing, especially a kind of nuclear radiation shield optimization of material method for designing.
Background technology:
The nuclear radiation shield material is the important component part of all kinds of nuclear facilities, is one of deciding factor that can nuclear science technology practice smooth implementation.
The method of production of traditional core radiation shielding material is through a large amount of Theoretical Calculation and professional experiences decision material substance proportioning, carries out technical study again, and then produces material sample, and the measurement that experimentizes, the shielding material of finally selecting is as approved product.The tradition method of production has long, deficiency such as raw material resources is wasteful of cycle.The more important thing is that traditional method of production is difficult to be extended in the nuclear radiation shield material development in other field.
Summary of the invention:
The objective of the invention is to overcome the shortcoming of above-mentioned prior art; A kind of nuclear radiation shield optimization of material method for designing is provided; Can realize neutron, the design of γ mixed radiation shielding material optimizing of components, make the development of nuclear radiation shield material cross the science economical by traditional type.It has overcome long, deficiency such as raw material resources is wasteful of traditional method of production cycle.This method can be designed light weight, volume is little, the nuclear radiation shield performance is good high performance material, is applicable to the component and the structure Design of nuclear radiation shield material, can be extended to nuclear fusion, nuclear waste disposal, and even field such as aerospace engineering.
Technical scheme of the present invention realizes through following steps:
A kind of nuclear radiation shield optimization of material method for designing comprises the steps:
(1) with the material mixture ratio initialization: confirm the component of the nuclear radiation shield material that designs, generate a material composition proportioning, calculate the proportioning of the various elements of forming these materials by genetic algorithm;
(2) the element proportioning that obtains according to step (1); Calculate respectively and characterize material shielding performance; The physical quantity of mechanics, thermal property and anti-radiation performance; As: the gamma-rays after the material shielding and accumulated dose equivalent, material thermal conductivity, material thermal expansion coefficient and the elasticity modulus of materials etc. of neutron, each is measured as sub-goal, provides each calculated value;
(3) to as a result behind the nondimensionalization, carrying out weighted sum according to design demand according to step (2);
(4) obtain the value of an optimization aim function according to step (3), this value is exactly a daughter in the genetic algorithm; Respective material proportioning adaptive character, with genetic algorithm this daughter is selected, is intersected and make a variation after can provide a new material composition proportioning, repeating step (1) again; Through cycle calculations, objective function will obtain an optimum value, the material mixture ratio after the output optimization.
In general, this optimum value is exactly the maximal value or the minimum value of objective function.The groundwork of this method is to do novel shielding material design; The accumulated dose equivalent of material after to the shielding of neutron and gamma-rays mixed sources is exactly leading factor; Choose bigger weight factor, and hope that its value is more little good more, just require the minimum value of optimization problem.So the weighted sum in the step 3) will be carried out proper mathematic treatment.
Annotate: 1. this method also can shield the single goal optimal design of back metering; 2. this method not only can be carried out the optimal design of material component, also can carry out the shield structure optimization design.
The creativeness of nuclear radiation shield optimization of material method for designing of the present invention is embodied in following aspect:
1) unfavorable factors such as the low or precocious convergence of OPTIMIZATION EFFICIENCY FOR GENETIC ALGORITHMS have been overcome through suitable selection genetic algorithm parameter;
2) realized that based on the Optimization Design of genetic algorithm the interface of genetic algorithm program and material property calculation procedure and shielding properties software for calculation handles, guaranteed optimal design realization process by genetic algorithm control;
3) in algorithm, needing recursive call correlator program, is the accuracy of taking into account calculating and the high efficiency of optimizing computing, has set up Simple and Reliable SHIELDING CALCULATION physical model, and in genetic algorithm, has launched skill such as data precision control;
4) multi-objective optimization design of power method key is the nondimensionalization of each aim parameter and the selection of weight factor, makes result of calculation have physical significance, meets the engineering actual conditions.
The beneficial effect that the present invention reached comprises:
1) can be optimized design to multiple material component;
2) be easy to be compiled into computer program and improve optimizing efficient, instruct the design and the production of novel nuclear radiation shield material effectively;
3) the multiple Effect on Performance of consideration shielding material can optimal design go out the good novel shielding material of combination property.
Description of drawings:
Fig. 1 is genetic algorithm optimization material movement figure of the present invention;
Fig. 2 is the curve map of the material thickness-accumulated dose equivalent of the PBa of being of the present invention, PBb, PBc and reference material;
Fig. 3 is multiple designing material sample of the present invention and reference material deep penetration shielding properties comparison diagram;
Fig. 4 is the accumulated dose-thickness map of five kinds of materials of the present invention.
Embodiment:
Below in conjunction with accompanying drawing the present invention is done and to describe in further detail:
Embodiment 1:
The optimal design of lead-boron polythene series material.
The stock component of selecting is tygon, boron carbide and lead.The objective function of optimizing is the accumulated dose equivalent after shielding.Constraint condition is the percentage composition of density He certain component of material.See table 5-1.
Further investigation genetic algorithm program GENOCOPII and MCNP software.As required they are done suitable improvement, the connection of being convenient to two programs be connected after operation.Utilize the C language to be implemented in and call MCNP software among the genetic algorithm program GENOCOPII, accomplish the debugging of whole algorithm.Then the material of being elected is optimized calculating.
The optimization results:
Result under first constraint condition of table 1 the inside is numbered PBa, and estimation density is 3.36gcm-3; Result under second constraint condition is numbered PBb, and estimation density is 3.84gcm-3; Result under the 3rd constraint condition is numbered PBc, and estimation density is 4.808gcm-3.
The trial result under several kinds of constraint conditions of table 1
Figure BDA0000140488080000031
The a of Fig. 2, b, c are respectively the curves of the material thickness-neutron source dose equivalent of the material of material PBa, PBb, the PBc contrast of putting together with seven kinds of comparative materials respectively.
Optimize material PBa because the restriction of constraint condition is reference with PB202, it is also very little with the PB202 difference to optimize the material composition that comes out, so both almost do not have difference on the shielding properties.The curve that is embodied on Fig. 2 both also overlaps basically.Had comparatively significantly and improved and relaxed the optimization material PBb that obtains after the restriction of constraint condition and the PBc PB202 that on accumulated dose equivalent after the shielding, all compares.
Embodiment 2:
The optimal design of polyester-based compound substance.
Choosing of component seen table 2, chooses the component in the table, and molecular formula and density together provide:
Available shielding material component under the table 2 polyester combination process
Figure BDA0000140488080000041
As required they are done suitable improvement, the connection of being convenient to two programs be connected after operation.Utilize the C language to be implemented in and call MCNP software among the genetic algorithm program GENOCOPII, accomplish the debugging of whole algorithm.Then the material of being elected is optimized calculating.Wherein, optimize index and be the accumulated dose equivalent of gamma-rays and neutron after the material shielding or total population, constraint condition is the density of material and the percentage composition of certain material.
The operation Optimized Program can obtain a series of fission neutrons; γ mixed radiation shielding material is optimized sample, and they have Jxa1 and the Jxa2 sample of polyamide as hardening agent, and acid anhydrides is as the Pb6 sample of hardening agent; Djy sample based on hip moulding technology; And not iron content, tungsten and plumbous polyamide as the Interlayer sample (corresponding cake1 among the figure, 2,3) of hardening agent.Because component also will be applied for a patent, so do not list herein.
Their shielding properties is by the MCNP programming check, referring to Fig. 3.
Table 3 has comprehensively provided some other performances of material.
Many kinds of designing material samples of table 3 and reference material main performance are relatively
Figure BDA0000140488080000051
It is thus clear that the material shielding performance that designs with this method is better than existing material.
Embodiment 3:
Multiple-objection optimization
The material component of selecting for use: epoxy resin, lithium carbonate, boron carbide, aluminium oxide, graphite, iron, gadolinium oxide, tungsten carbide, lead, nano titanium oxide.
The target of choosing is respectively the shielding properties of material, thermal conductivity, thermal expansivity, elastic modulus.Calculate by experiment flow shown in Figure 1.
Result of calculation.
Being numbered three kinds of materials of 1,2,3 corresponds respectively to: first kind of objective function weight coefficient α gets 0.8, the second kind of objective function weight coefficient α and gets 0.9, and the third objective function weight coefficient α gets 0.9.Comparative material is elected PB202 and Cake1 as.
Table 4 has provided the rerum natura performance parameter through each material of MCNP check, and Fig. 4 has provided the comparison of the shield effectiveness of five kinds of materials above-mentioned.
Table 4 is through the rerum natura performance parameter of each material of MCNP check
Figure BDA0000140488080000061
The effect of invention
Use the material that this method is designed, its shielding properties is stood the check of analog computation and experiment: utilize the material thickness of MCNP program calculation optimization gained material-through the dose equivalent curve; Compare with the curve of existing other more representational shielding material, prove credible result and the better effects if optimizing out.
The big content of starting materials of traditional material development waste, manpower, money and the deficiency of time have been avoided.Optimize that the quality of materials that is light, volume is little, advantages of good shielding performance.Simultaneously, the mechanics of materials and the calorifics designed are better.
Fig. 1 is a schematic flow sheet of the present invention; Fig. 2 is the curve of the material thickness-accumulated dose equivalent of PBa, PBb, PBc and reference material, corresponding embodiment 1; Fig. 3 is that multiple designing material sample and reference material deep penetration shielding properties compare corresponding embodiment 2;
The above only is preferred embodiment of the present invention, is not the present invention is done any pro forma restriction; Though the present invention discloses as above with preferred embodiment; Yet be not in order to limiting the present invention, anyly be familiar with the professional and technical personnel, in not breaking away from technical scheme scope of the present invention; When the method for above-mentioned announcement capable of using and technology contents are made a little change or be modified to the equivalent embodiment of equivalent variations; In every case be the content that does not break away from technical scheme of the present invention, to any simple modification, equivalent variations and modification that above embodiment did, still belong in the scope of technical scheme of the present invention according to technical spirit of the present invention.

Claims (5)

1. a nuclear radiation shield optimization of material method for designing is characterized in that, comprises the steps:
(1) with the material mixture ratio initialization: confirm the component of the nuclear radiation shield material that designs, generate a material composition proportioning, calculate the proportioning of the various elements of forming these materials by genetic algorithm;
(2) the element proportioning that obtains according to step (1) is calculated respectively and is characterized material shielding performance, the physical quantity of mechanics, thermal property and anti-radiation performance;
(3) to carrying out weighted sum behind the nondimensionalization as a result according to step (2);
(4) obtain the value of an optimization aim function according to step (3), this value is exactly a daughter in the genetic algorithm; Respective material proportioning adaptive character, with genetic algorithm this daughter is selected, is intersected and make a variation after can provide a new material composition proportioning, repeating step (1) again; Through cycle calculations, objective function will obtain an optimum value, the material mixture ratio after the output optimization.
2. nuclear radiation shield optimization of material method for designing according to claim 1 is characterized in that: be the application of genetic algorithm program in the said step (1), generate an initial material composition proportioning, write out an input file that has constraint condition on request.
3. nuclear radiation shield optimization of material method for designing according to claim 1, it is characterized in that: said step (2) is the selection and the calculating of sub-goal, and these sub-goals can be represented shielding properties, mechanics, calorifics and the anti-radiation performance of material; Realize the foundation of sub-goal model and result's output, and carry out interface with genetic algorithm program.
4. nuclear radiation shield optimization of material method for designing according to claim 1; It is characterized in that: said step (3) is the use of nondimensionalization method and choosing of weight coefficient; Wherein nondimensionalization is to calculate accurately in order to guarantee, the selection of weight coefficient is in order to adapt to designing requirement.
5. nuclear radiation shield optimization of material method for designing according to claim 1, it is characterized in that: said step (4) is the realization of loop calculation, and the generation of new material mixture ratio is to guarantee that result calculated is that direction towards expection develops.
CN201210054251.9A 2012-03-05 2012-03-05 Nuclear radiation shielding material optimization design method Expired - Fee Related CN102663151B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201210054251.9A CN102663151B (en) 2012-03-05 2012-03-05 Nuclear radiation shielding material optimization design method

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201210054251.9A CN102663151B (en) 2012-03-05 2012-03-05 Nuclear radiation shielding material optimization design method

Publications (2)

Publication Number Publication Date
CN102663151A true CN102663151A (en) 2012-09-12
CN102663151B CN102663151B (en) 2014-04-23

Family

ID=46772642

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201210054251.9A Expired - Fee Related CN102663151B (en) 2012-03-05 2012-03-05 Nuclear radiation shielding material optimization design method

Country Status (1)

Country Link
CN (1) CN102663151B (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104103330A (en) * 2014-04-04 2014-10-15 西安交通大学 Nuclear radiation shielding material
CN109243654A (en) * 2018-10-10 2019-01-18 镇江华核装备有限公司 A kind of preparation process of nuclear leakage emergency screening clothing
CN110955995A (en) * 2019-11-25 2020-04-03 上海理工大学 Optimization design method of broadband damping composite material
CN111859804A (en) * 2020-07-20 2020-10-30 西安交通大学 Multi-target radiation shielding design method

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2006017247A2 (en) * 2004-07-13 2006-02-16 Kimotion Technologies Method and apparatus for designing electronic circuits using optimization
CN101567020A (en) * 2009-05-08 2009-10-28 江苏大学 Optimization method for mixture ratio of components of working layer of metal plastic composite material

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2006017247A2 (en) * 2004-07-13 2006-02-16 Kimotion Technologies Method and apparatus for designing electronic circuits using optimization
CN101567020A (en) * 2009-05-08 2009-10-28 江苏大学 Optimization method for mixture ratio of components of working layer of metal plastic composite material

Non-Patent Citations (3)

* Cited by examiner, † Cited by third party
Title
《IEEE Transaction on Nuclear Science》 20080831 Hu Huasi等 Study on Composite Material for Shielding Mixed Neutron and gamma-Rays 第55卷, 第4期 *
HU HUASI等: "Study on Composite Material for Shielding Mixed Neutron and γ-Rays", 《IEEE TRANSACTION ON NUCLEAR SCIENCE》 *
胡华四等: "新型核辐射屏蔽材料的优化设计", 《原子能科学技术》 *

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104103330A (en) * 2014-04-04 2014-10-15 西安交通大学 Nuclear radiation shielding material
CN109243654A (en) * 2018-10-10 2019-01-18 镇江华核装备有限公司 A kind of preparation process of nuclear leakage emergency screening clothing
CN110955995A (en) * 2019-11-25 2020-04-03 上海理工大学 Optimization design method of broadband damping composite material
CN110955995B (en) * 2019-11-25 2023-04-18 上海理工大学 Optimization design method for broadband damping composite material
CN111859804A (en) * 2020-07-20 2020-10-30 西安交通大学 Multi-target radiation shielding design method

Also Published As

Publication number Publication date
CN102663151B (en) 2014-04-23

Similar Documents

Publication Publication Date Title
CN102663151B (en) Nuclear radiation shielding material optimization design method
CN107038294B (en) For the Resonance self-shielding calculation method based on equivalent one-dimensional stick model of light water reactor
Le Tellier et al. High-order discrete ordinate transport in hexagonal geometry: a new capability in ERANOS
Kochunas et al. VERA core simulator methodology for PWR cycle depletion
CN106126928B (en) Obtain solid-state and the method and database of liquid villiaumite thermal neutron scattering database
Deng et al. Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor
Daeubler et al. Development of a high-fidelity Monte Carlo thermal-hydraulics coupled code system Serpent/SUBCHANFLOW–first results
Kim et al. Development of the CASL-VERA V4. 2m5 MPACT 51-group Libraries with ENDF/B-VII. 0 and VII. 1
Akopov et al. Application of the two-scale model to the HERMES data on nuclear attenuation
CN106295213A (en) A kind of iteration based on particle density inhomogeneities is covered card overall situation power window parameter and is generated method
Xu et al. Burnable poison selection and neutronics analysis of plate fuel assemblies
Choi et al. Conceptual design of thorium based epithermal spectrum reactor
Collins et al. Coupled Simulations of Fast-Spectrum Molten Salt Reactors
Motalab et al. Use of Er burnable absorber for improvement of CANDU6 safety parameters
Bungau et al. Neutron spallation studies for an accelerator driven subcritical reactor
Pandey et al. Excitation functions of (n, p) reactions for stable isotopes of Cr, Fe and Ni from threshold to 20 MeV
Newman et al. Maximum rate for the proton-proton reaction compatible with conventional solar models
Henderson et al. Coupled deterministic and Monte Carlo neutronics for vessel fluence calculations
Żmuda et al. Electroweak single pion production and form factors of the Δ (1232) resonance
Tsukiyama et al. Shine-III: simple code for skyshine dose calculation up to 3GeV neutrons
Li et al. Burnup analysis of the pebble-bed fluoride-salt-cooled high-temperature reactor based on the Chord Length Sampling method
Liu et al. Recycling of Critical Metals in Green and Low-carbon Transition: Strategies and Countermeasures
Hu et al. Development and Applications of Nuclear Design and Safety Assessment Program SuperMC for Fast Reactoron
Sun Multi-indicator Evaluation and Analysis of Coordinated Industrial Development of Urban Agglomerations
Jang et al. Analysis of Rostov-II Benchmark Using Conventional Two-Step Code Systems. Energies 2022, 15, 3318

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
C14 Grant of patent or utility model
GR01 Patent grant
CF01 Termination of patent right due to non-payment of annual fee
CF01 Termination of patent right due to non-payment of annual fee

Granted publication date: 20140423

Termination date: 20180305