Estimation of Tritium Permeation Rate to Cooling Water in Fusion DEMO Condition-Reference-Cited by-同舟云学术

Estimation of Tritium Permeation Rate to Cooling Water in Fusion DEMO Condition

Published:2017-03-02 Issue:3 Volume:71 Page:261-267
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Katayama Kazunari¹,Someya Youji²,Tobita Kenji²,Nakamura Hirofumi³,Tanigawa Hisashi²,Nakamura Makoto²,Asakura Nobuyuki²,Hoshino Kazuo²,Chikada Takumi⁴,Hatano Yuji⁵,Fukada Satoshi¹

Affiliation:

1. Department of Advanced Energy Engineering Science, Kyushu University, Kasuga, Fukuoka, Japan

2. National Institutes for Quantum and Radiological Science and Technology, Rokkasho, Aomori, Japan

3. National Institutes for Quantum and Radiological Science and Technology, Tokai-mura, Ibaraki, Japan

4. Graduate School of Science, Shizuoka University, Shizuoka, Japan

5. Hydrogen Isotope Research Center, University of Toyama, Toyama, Japan

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/10.1080/15361055.2017.1288423

Reference5 articles.

1. Tritium Breeding Ratio Required to Keep Tritium Balance in a D-T Fusion Reactor

2. Y. UEDA, “Status of Plasma Facing Material Studies and Issues toward DEMO,” Proc. 18th International Toki Conference, Toki-city, Gifu, Japan, December 9–12, 2008.

3. A simple theory for maximum h inventory and release: A new transport parameter

4. Steady state hydrogen transport in solids exposed to fusion reactor plasmas, part II: Applications of theory

5. Hydrogen transport behavior of metal coatings for plasma-facing components

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