Recent Advances on Hydrogen Retention in ITER’s Plasma-Facing Materials: Beryllium, Carbon, and Tungsten-Reference-Cited by-同舟云学术

Recent Advances on Hydrogen Retention in ITER’s Plasma-Facing Materials: Beryllium, Carbon, and Tungsten

Published:2008-11 Issue:4 Volume:54 Page:891-945
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Skinner C. H.¹,Haasz A. A.²,Alimov V. Kh.³,Bekris N.⁴,Causey R. A.⁵,Clark R. E. H.⁶,Coad J. P.⁷,Davis J. W.²,Doerner R. P.⁸,Mayer M.⁹,Pisarev A.¹⁰,Roth J.⁹,Tanabe T.¹¹

Affiliation:

1. Princeton Plasma Physics Laboratory, Princeton, New Jersey

2. University of Toronto Institute for Aerospace Studies, Toronto, Ontario, Canada

3. Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences, Moscow, Russia

4. Forschungszentrum Karlsruhe, Karlsruhe, Germany

5. Sandia National Laboratories, Livermore, California

6. IAEA Atomic and Molecular Data Unit, Vienna, Austria

7. EURATOM0UKAEA Fusion Association, Culham Science Centre, Abingdon, OX14 3DB, United Kingdom

8. University of California, San Diego, California

9. Max-Planck-Institut für Plasmaphysik, EURATOM Association, Garching, Germany

10. Moscow State Engineering and Physics Institute, Moscow, Russia

11. Interdisciplinary Graduate School of Engineering Science, Kyushu University, 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/10.13182/FST54-891

Reference273 articles.

1. “12th Meeting of the IFRC Subcommittee on Atomic and Molecular Data for Fusion,” International Atomic Energy Agency Summary Report INDC(NDS)-420, available on the Internetat http://www-nds.iaea.org/reports-new/indc-reports/indc-nds/indc-nds-0420.pdf (2000).

2. Tritium Inventory in the Materials of the ITER Plasma-Facing Components

3. Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

4. Hydrogen isotope retention and recycling in fusion reactor plasma-facing components

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