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聚变堆第一壁辐照效应研究 被引量:3

THE IRRADIATION EFFECTS INVESTIGATION OF FIRST WALL FOR FUSION REACTORS
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摘要 本文简要介绍了聚变堆第一壁材料的辐照效应,研究了混合堆设计中CHD、TETB和TCB第一壁材料的辐照损伤问题,给出了原子位移率、嬗变气体产生率和肿胀率等的有关计算结果。预言了在设计条件下混合堆第一壁的辐照寿命。本文的结果可供第一壁材料在比较和选择时参考。 The irradiation effects of first wall materials for fusion reaclors are introduced in this paper.The atomic displacement damage transmuted helium and hydrogen production rate and swelling rate of materials are investigated for several hybrid reactor conceptual designs.The radiation environment of the hybrid reactors are also prcdicted. These results should be useful for comparison and selection of first wall materials in fusion reactor design.
作者 冯开明
出处 《核科学与工程》 CSCD 北大核心 1991年第4期318-324,5,共7页 Nuclear Science and Engineering
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参考文献3

  • 1黄锦华,盛光昭,施汉文,游承伦,谢中友,邓柏权,冯开明,王学人,薛淑兰,王庆明,黄中琪,张飚,阳彦鑫,吴灵桥,张丽,张国书,吕晓兰,霍铁军.托卡马克工程试验混合堆概念设计[J].核聚变与等离子体物理,1990,10(4):193-208. 被引量:7
  • 2黄锦华,1989年
  • 3黄锦华,核科学与工程,1987年,7卷,2期,164页

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  • 1肖建军,周志伟,杨永伟,经荥清.ITER中国固体实验包层温度场数值模拟[J].清华大学学报(自然科学版),2006,46(3):437-440. 被引量:4
  • 2刘春海,杜晓松,汪德志,黄宁康,杨斌.H^+辐照前后Mo涂层表面的XPS分析[J].功能材料,2007,38(2):176-178. 被引量:2
  • 3ITER TBWG Members.Report from the reestablished test blanket working group for the period of the ITER transitional arrangements(1TA)[R].[S.l.]:[s.n.],2005.
  • 4ITER Documents.Structural design criteria for ITER in-vessel components(SDC-IC),Appendix A:Materials design limit data,G74MA8R0.1[R].[S.l.]:[s.n.],2004.
  • 5Xu N. , Sun M. , Cao Y. W. , et al. Influence of PH on Structure and Photochromic Behavior of Nanocrystalline WO3 Films [ J ]. Appl. Sur. Sci. ,2000,157:81 - 84.
  • 6R. Kemp. Alloy Design for a Fusion Power Plant. Submitted for the degree of Doctor of Philosophy at the University of Cambridge, May 2006 : 54 - 57.
  • 7蔡瑜.表面工程技术工艺方法400种[M].北京:机械工业出版社,2006:2-10.
  • 8M. Rubel. Fusion Reactor Materials And Components:Issues Related To Radioactivity And Radiation Induced Effects. Transactions of Fusion Science and Technology ,2004,45:32 - 35.
  • 9S. Nageta, K. Takahiro, S. Horiike, S. Yamaguchi. Retention and release of deuterium implanted ion W and Mo [J]. J. Nuel. Mater. , 1999, 266-269:1 151-1 156.
  • 10A. Aiello, A. Ciampichetti, G. Benamati. An overview on tritium permeation barrier development for WCLL blanket concept [ J ]. Journal of Nuclear Materials. 2004(2 -5) :1 388 - 1 402.

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