期刊文献+

ITER氚增殖实验包层设计研究进展 被引量:8

Progress in design and study of ITER test blanket modules
下载PDF
导出
摘要 国际热核实验反应堆(ITER)为人类开发聚变能提供重要的物理和工程技术实验平台,ITER氚增殖实验包层模块(TBM)技术是必须掌握的关键技术。参与ITER计划的成员国根据本国商用演示堆包层发展策略,分别提出了各自的实验包层概念,以便在ITER运行期间进行实验。本文对ITER-TBM目前已经开展和正在进行的主要设计研究工作进展进行总结,介绍了各方提出的设计方案、支撑设计的相关技术研究进展,以及合作实验窗口的分配现状。 The International Thermonuclear Experimental Reactor (ITER) will be the first experimental D-T fusion reactor to provide an exclusive test platform of physics and engineering technology for research and development of fusion, where the technology of Test Blanket Module (TBM) in ITER is one of the most critical kernels to achieve fusion power in the future. According to defined concepts of DEMO blanket, the parties had proposed DEMO-relevant TBM, respectively, which would be to be tested during ITER operation. Design of proposed TBM concepts, R&D status, and recommended port allocation in ITER are introduced in this contribution.
出处 《核科学与工程》 CSCD 北大核心 2009年第3期266-272,共7页 Nuclear Science and Engineering
基金 国家自然科学基金项目(10675123 50805138 10775135 50871108 10875145)
关键词 聚变能 国际热核实验堆 实验包层模块 fusion energy international thermonuclear experimental reactor test blan-ket module
  • 相关文献

参考文献36

  • 1Chuyanov V A , ITER Test Blanket Working Group. ITER Test Blanket Working Group activities: a summary, recommendations and conclusions[J]. Fusion Eng Des, 2002, 61-62:273-281.
  • 2Minutes of the 17th Meeting of the TBWG (TBWG-17) JWS/Cadarache, April 4-6th, 2006. https: //user. iter. org.
  • 3Giancarli I. , Chuyanov V , Abdou M , et al. Test blanket modules in ITER: An overview on proposed designs and required DEMO relevant materials[J]. Journal of Nuclear Materials, 2007, 367-370: 1271-1280.
  • 4柏云清,陈红丽,刘松林,宋勇,曾勤,黄群英,吴宜灿.聚变堆增殖包层概念特征比较研究[J].核科学与工程,2008,28(3):249-255. 被引量:11
  • 5Cismondi F , Kecskes S , Ilic M , et al. Design update, thermal and fluid dynamic analyses of the EU HCPB TBM in vertical arrangement [J]. Fusion Eng Des, 2009, 84: 607-612.
  • 6Salavy J F , Boccaccini L V , Lasser R. Overview of-the last progresses for the European Test Blanket Modules projects[J]. Fusicon Eng Des, 2007 ,82:2105-2112.
  • 7Seungyon Cho, Duck-Hoi Kim, Mu-Young Ahn. Development of low activation ferritic/martensitie steel welding technology for the fabrication of KO HCSB TBM [J]. Journal of Nuclear Material, 2009, 386-388:491-494.
  • 8Bong Geun Hong, Dong Won Lee, Son Jong Wang, et al. Basic concepts of DEMO and a design of a helium cooled molten lithium blanket for a testing in ITER[J]. Fusion Eng Des, 2007,82 : 2399-2405.
  • 9Feng K M , Pan C H , Zhang G S , et al. Overview of design and R&D of solid breeder TBM in China[J]. Fusion Eng Des, 2008, 83:1149-1156.
  • 10Wu Y, FDS Team. Design Concept and Testing Strategy of a Dual Functional Lithium Lead Test Blanket Module in ITER and EAST[J]. Nucl Fusion, 2007, 47:1533-1539.

二级参考文献163

共引文献213

同被引文献60

引证文献8

二级引证文献13

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部