Diffusion Coefficient of Tritium Through Molten Salt Flibe and Rate of Tritium Leak from Fusion Reactor System-Reference-Cited by-同舟云学术

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Diffusion Coefficient of Tritium Through Molten Salt Flibe and Rate of Tritium Leak from Fusion Reactor System

Published:2005-08 Issue:1 Volume:48 Page:666-669
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Fukada Satoshi¹,Anderl Robert A.²,Sagara Akio³,Nishikawa Masabumi¹

Affiliation:

1. Kyushu University, Hakozaki, Fukuoka 812-8581, Japan, sfukada@nucl.kyushu-u.ac.jp, nishikaw@nucl.kyushu-u.

2. Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID 83415-7113, USA, raa@inel.gov

3. National Institute for Fusion Science, Toki 509-5292, Japan, sagara.akio@nifs.ac.jp

Publisher

Informa UK Limited

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Civil and Structural Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/FST05-A1013

Reference12 articles.

1. Studies on Flibe Blanket Designs in Helical Reactor FFHR

2. Deuterium/tritium behavior in Flibe and Flibe-facing materials

3. Initial studies of tritium behavior in flibe and flibe-facing material

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