An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility

P. Calderoni, J. Sharpe, M. Shimada, B. Denny, B. Pawelko, S. Schuetz, G. Longhurst, Y. Hatano, M. Hara, Y. Oya, T. Otsuka, K. Katayama, S. Konishi, K. Noborio, Y. Yamamoto

研究成果: Contribution to journalArticle査読

5 被引用数 (Scopus)

抄録

The Safety, Tritium and Applied Research facility at the Idaho National Laboratory is a US Department of Energy National User Facility engaged in various aspects of materials research for nuclear applications related to fusion and advanced fission systems. Research activities are mainly focused on the interaction of tritium with materials, in particular plasma facing components, liquid breeders, high temperature coolants, fuel cladding, cooling and blanket structures and heat exchangers. Other activities include validation and verification experiments in support of the Fusion Safety Program, such as beryllium dust reactivity and dust transport in vacuum vessels, and support of Advanced Test Reactor irradiation experiments. This paper presents an overview of the programs engaged in the activities, which include the US-Japan TITAN collaboration, the US ITER program, the Next Generation Power Plant program and the tritium production program, and a presentation of ongoing experiments as well as a summary of recent results with emphasis on fusion relevant materials.

本文言語英語
ページ(範囲)1336-1340
ページ数5
ジャーナルJournal of Nuclear Materials
417
1-3
DOI
出版ステータス出版済み - 10 1 2011

All Science Journal Classification (ASJC) codes

  • 核物理学および高エネルギー物理学
  • 材料科学(全般)
  • 原子力エネルギーおよび原子力工学

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