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HCSB-DEMO等离子体参数的确定与初步分析 被引量:3

Primary analyses of plasma parameters for HCSB-DEMO reactor
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摘要 根据HCSB-DEMO堆的设计要求,对不同尺寸的聚变堆能产生的聚变功率、中子壁负载和等离子体燃烧时间等进行计算与分析,给出了符合设计要求的堆芯参数。在所选定的堆芯参数条件下进行了零维功率平衡计算分析,给出了3组HCSB-DEMO堆的等离子体初步设计参数。 Due to the requirements of HCSB-DEMO reactor design, fusion powers, neutron wall loadings and plasma burn times in the fusion reactors with different sizes are investigated. Reactor parameters are selected and analyzed with the POPCON code. Three group plasma parameters suitable for HCSB-DEMO reactor are given.
出处 《核聚变与等离子体物理》 EI CAS CSCD 北大核心 2007年第3期212-216,共5页 Nuclear Fusion and Plasma Physics
关键词 中子壁负载 运行时间 聚变功率 聚变示范堆 Neutron wall loading Plasma burn time Fusion power HCSB-DEMO
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参考文献16

  • 1Strebkov Yu. RF definition of DEMO reactor and strategy [R]. Test Blanket Working Group Meeting (TBWG- 12) Naka, Japan, Mach 10-11, 2004.
  • 2Boccaccini L V, DEMO development strategy in EU [R] Test Blanket Working Group Meeting (TBWG-12) Naka, Japan, Mach 10-11, 2004.
  • 3Akiba M. DEMO definition of Japan [R]. Test Blanket Working Group Meeting (TBWG-12) Naka, Japan, Mach 10-11, 2004.
  • 4Hiwatari R, Okano K, Asaoka Y,et al. Demonstration tokamak fusion power plant for early realization of net electric power generation [R]. Vienna: IAEA, 2005.
  • 5PAN Chuanhong. Definition of DEMO reactor and DEMO development strategy in CH [R] Test Blanket Working Group Meeting (TBWG-12) Naka, Japan, Mach 10-11, 2004.
  • 6盛光昭,STR参数分析研究[R].成部:核工业西南物理研究院,1994.
  • 7Stacey W M. Tokamak demonstration reactors [J], Nucl. Fusion, 1995, 35: 11.
  • 8ITER Physics Basis Editors, ITER Physics Expert Group Chairs and Co-Chairs, ITER Joint Central Team and Physics Integration Unit. Chapter 1: Overview and summary [J]. Nucl. Fusion, 1999, 39(12): 2137.
  • 9ITER Physics Expert Group on Disruptions, Plasma Control and MHD, ITER Physics Basis Editors. Chapter 3: MHD stability, operational limits and disruptions [J]. Nucl. Fusion, 1999, 39(12): 2251.
  • 10Clement Wong. General atomics system study of superconducting coils fusion devices at different aspect ratios [Z]. Private letter, 2005.

二级参考文献1

同被引文献21

  • 1唐晓寅,张赞牢,王建华,黄磊.管道热边界层理论的研究[J].后勤工程学院学报,2006,22(1):45-49. 被引量:8
  • 2贾小波,杨永伟,周志伟,经荥清,冯开明,张国书.ITER中国固态TBM中子倍增剂和氚增殖剂布置优化[J].清华大学学报(自然科学版),2006,46(9):1629-1632. 被引量:2
  • 3Pan C H, Wu Y C, Feng K M, et al. DEMO development strategy based on China FPP program [J]. Fusion Engineering and Design, 2008, 83: 877-882.
  • 4Feng K M~ Zhang G S, Zheng GY, et al. Conceptual design study of fusion DEMO plant at SWIP [J]. Fusion Engineering and Design, 2009, 84(12): 2109-2113.
  • 5Feng K M, Pan C H, Zhang G S, et al. Preliminary design for a China ITER test blanket module [J]. Fusion Engineering and Design, 2006, 81(8-14): 1219-1224.
  • 6赵周,冯开明,王晓宇,等.ITER氦冷固态增殖剂试验包层模块设计子模块热工水力分析[R].成都:核工业西南物理研究院年报,2005.91-92.
  • 7Wang Pinghuai. Characterization of CLF-t steel [R].成都:核工业西南物理研究院,2009.
  • 8Xu Z, Meyder R, Boccaccini L V. Design and validation of breeder unit of helium-cooled pebble bed blanket for demo fusion reactor [J]. Fusion Engineering and Design, 2006, 81(19): 2233-2238.
  • 9陈志.试验包层模块(TBM)安全分析中的参数选择[R].成都:核工业西南物理研究院年报,2004.72-73.
  • 10Bekris N, Boccaccini L V, Dolenski S, et al. Design description document for the European helium cooled pebble bed(HCPB) test blanket mottules JR]. Karlsruhe: Karlsruhe Forschungszentrum, 2005.

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