Recent Advances on Hydrogen Retention in ITER’s Plasma-Facing Materials: Beryllium, Carbon, and Tungsten
| Autor: | Tetsuo Tanabe, R. P. Doerner, N. Bekris, J. Roth, C. H. Skinner, A.A. Haasz, J. P. Coad, R. E. H. Clark, R. A. Causey, J.W. Davis, M. Mayer, V.Kh. Alimov, A. Pisarev |
|---|---|
| Rok vydání: | 2008 |
| Předmět: |
Nuclear and High Energy Physics
Materials science Hydrogen 020209 energy Mechanical Engineering Nuclear engineering chemistry.chemical_element Magnetic confinement fusion 02 engineering and technology Fusion power Tungsten 01 natural sciences 010305 fluids & plasmas Nuclear Energy and Engineering chemistry 0103 physical sciences 0202 electrical engineering electronic engineering information engineering General Materials Science Tritium Beryllium Atomic physics Porosity Carbon Civil and Structural Engineering |
| Zdroj: | Scopus-Elsevier Fusion Science and Technology |
| ISSN: | 1943-7641 1536-1055 |
| DOI: | 10.13182/fst54-891 |
| Popis: | 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 ITER’s plasma-facing materials – Be, C, and W – and in compounds (mixed materials) of these elements as well as tritium removal techniques. The results of the CRP are summarized in this paper 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. Codeposition is also the dominant retention mechanism for carbon and remains a serious concern f... |
| Databáze: | OpenAIRE |
| Externí odkaz: |
|