Recent Advances on Hydrogenic Retention in ITER'S Plasma-Facing Materials: Be, C, W.

Skinner, C. H. ; Haasz, A. A. ; Alimov, V. K. ; Bekris, N. ; Causey, R. A. ; Coad, J. P.

Technical Information Center Oak Ridge Tennessee

关键词: Hydrogen retention;    Tritium inventory;    ITER tokamak;    Fusion reactors;    Beryllium;   

RP-ID  :  DE2009959393

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

Management of tritium inventory remains one of the grand challenges in the development of fusion energy and the choice of plasma-facing materials is a key factor for in-vessel tritium retention. The Atomic and Molecular Data Unit of the International Atomic Energy Agency organized a Coordinated Research Project (CRP) on the overall topic of tritium inventory in fusion reactors during the period 2001-2006. This dealt with hydrogenic retention in ITERs plasma-facing materials, Be, C, W, and in compounds (mixed materials) of these elements as well as tritium removal techniques. The results of the CRP are summarized in this article together with recommendations for ITER. Basic parameters of diffusivity, solubility and trapping in Be, C and W are reviewed. For Be, the development of open porosity can account for transient hydrogenic pumping but long term retention will be dominated by codeposition.