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国际热核聚变堆实验增殖包层模块设计
引用本文:王少华,黄洪文,曾和荣,刘志勇.国际热核聚变堆实验增殖包层模块设计[J].强激光与粒子束,2015,27(1):016011.
作者姓名:王少华  黄洪文  曾和荣  刘志勇
作者单位:1.中国工程物理研究院 核物理与化学研究所, 四川 绵阳 621 900
基金项目:国家磁约束核聚变能研究专项(2012GB106001)
摘    要:为了验证国际热核聚变堆(ITER)的产氚和能量获取等性能,各国分别提出了不同的实验增殖模块(TBM)设计方案。其总体功能相同,但具体技术路线有区别,不同之处包括冷却剂选择、产氚材料选择、中子倍增剂选择、产氚区布置形式、面向等离子体材料选择、结构材料选择等方面。通过对各TBM方案进行比较分析,评价了各自的优缺点,提出了未来先进产氚包层方案的设计建议。

关 键 词:热核反应堆    实验增殖包层    材料    物理热工
收稿时间:2014/6/29

Overview of international thermonuclear experimental reactor test blanket module design
Wang Shaohua , Huang Hongwen , Zeng Herong , Liu Zhiyong.Overview of international thermonuclear experimental reactor test blanket module design[J].High Power Laser and Particle Beams,2015,27(1):016011.
Authors:Wang Shaohua  Huang Hongwen  Zeng Herong  Liu Zhiyong
Institution:1.Institute of Nuclear Physics and Chemistry,CAEP,Mianyang 621900,China
Abstract:The Test Blanket Module (TBM) Program has come into the engineering stage with the advance of the ITER project, and the basic TBM design of each ITER member has been fixed. All the TBMs share the same overall objectives, but differ in detailed designs, such as the coolant, tritium breeder, neutron multiplier, plasma facing components material and structural material, etc. The choices of the TBM designs are compared, the advantages and disadvantages of different choices are analyzed.
Keywords:international thermonuclear experimental reactor  test blanket module  materials  neutronic-hydraulic
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