聚变核数据库在水冷包层模块中子学特性模拟的影响研究
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- 英文论文题名：Influence on water cooled breeder blanket neutronics simulation with different fusion nuclear data libraries
- 论文作者：刘辰 ; 曹学武
- 英文论文作者：LIU Chen ; CAO Xue-wu ; School of Mechanical Engineering ; Shanghai Jiao Tong University
- 年：2015
- 作者机构：上海交通大学机械与动力工程学院;
- 论文关键词：水冷增殖包层 ; TBR ; 数据库 ; 中子模拟
- 英文论文关键词：water cooled breeder blanket ; TBR ; data library ; neutronics simulations
- 会议召开时间：2015-09-21
- 会议录名称：中国核科学技术进展报告（第四卷）——中国核学会2015年学术年会论文集第7册（计算物理分卷、核物理分卷、粒子加速器分卷、核聚变与等离子体物理分卷、脉冲功率技术及其应用分卷、辐射物理分卷）
- 语种：中文
- 分类号：TL64
- 学会代码：EGVD
- 会议名称：中国核学会2015年学术年会
- 会议地点：中国四川绵阳
- 主办单位：中国核学会
- 学会名称：中国核学会
- 页数：5
- 文件大小：225k
- 原文格式：O
- 会议级别：全国
摘要
水冷增殖包层是中国工程实验聚变堆(CFETR)的候选包层之一,包层模块的中子输运模拟对包层的设计是至关重要的,模拟中选用的聚变核数据库也会对模拟结果的产生影响。本文利用蒙特卡罗程序MCNP,参考JAERI关于锂壳的产氚实验装置建立了锂球壳模型,同时还参考日本JAEA的水冷包层设计建立了包层的一维球壳模型,分别采用FENDL2.1、FENDL3.0和JEFF 3.2三个数据库进行了中子输运模拟,计算了总氚增殖率(TBR)。模拟结果分别与锂球壳实验数据及水冷包层设计参数进行对比分析,表明FENDL3.0或JEFF 3.2可以作为水冷包层模块三维中子模拟的核数据库。
Water Cooled Breeder Blanket is one of the breeder blanket candidates for China Fusion Engineering Test Reactor(CFETR),and the neutron transport simulation of blanket module is significant for the blanket design.The selection of fusion nuclear data libraries impacts on the simulation results.The simple Li sphere model is built based on the experimental facility of tritium production about Li sphere shell constructed by JAERI,and the 1D sphere model of blanket is built referring to JAEA water cooled blanket design using the neutron transport Monte Carlo code MCNP.The neutronics simulations are carried out with FENDL 2.1,FENDL 3.0 and JEFF 3.2 to obtain tritium breeding ration(TBR),which is compared with experimental results and design parameters respectively.The results shows that the FENDL 3.0 or JEFF 3.2 is the selected data libraries for 3D neutronics simulation of blanket module.
Water Cooled Breeder Blanket is one of the breeder blanket candidates for China Fusion Engineering Test Reactor(CFETR),and the neutron transport simulation of blanket module is significant for the blanket design.The selection of fusion nuclear data libraries impacts on the simulation results.The simple Li sphere model is built based on the experimental facility of tritium production about Li sphere shell constructed by JAERI,and the 1D sphere model of blanket is built referring to JAEA water cooled blanket design using the neutron transport Monte Carlo code MCNP.The neutronics simulations are carried out with FENDL 2.1,FENDL 3.0 and JEFF 3.2 to obtain tritium breeding ration(TBR),which is compared with experimental results and design parameters respectively.The results shows that the FENDL 3.0 or JEFF 3.2 is the selected data libraries for 3D neutronics simulation of blanket module.
引文
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[7]JAERI.Design Description Document for the Japan Water Cooled Solid Breeder Test Blanket System[R].2005:39-50
[8]Sharma A R,et al.Analysis of integral benchmark experiments with lastest evaluated nuclear data[J].Journal of NUCLEAR SCIENCE and TECHNOLOGY,2002,2:1151-1154.
[2]Mikio E,et al.Overview of design and R&D of test blankets in Japan[J].Fusion Engineering and Design.2006,81:415-424.
[3]Poitevin Y,et al.Status of the design and performances of the WCLL test blanket module for ITER-FEAT[J].Fusion Engineering and Design.2002,62:431-437.
[4]X-5 Monte Carlo Team,MCNP-A General Monte Carlo N-Particle Transport Code,Version 5,LA,2003.
[5]Chikara K,et al.Analyses of fusion integral benchmark experiments at JAEA/FNS with FENDL-2.1 and other recent nuclear data libraries[J].Fusion Engineering and Design,2008,83:1774-1781.
[6]Iguchi T,et al.Tritium breeding ratio in Li,Pb-Li,Pb-Li-C,Be-Li,Be-Li-C spheres measured with Li_2CO_3pellets and/or LiF TLDs[R].JAERI-M-94-014,1994:6-9.
[7]JAERI.Design Description Document for the Japan Water Cooled Solid Breeder Test Blanket System[R].2005:39-50
[8]Sharma A R,et al.Analysis of integral benchmark experiments with lastest evaluated nuclear data[J].Journal of NUCLEAR SCIENCE and TECHNOLOGY,2002,2:1151-1154.