Release Behavior of Tritium from Graphite Material-Reference-Cited by-同舟云学术

Release Behavior of Tritium from Graphite Material

Published:2002-01 Issue:1 Volume:41 Page:53-62
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Katayama Kazunari¹,Nishikawa Masabumi¹

Affiliation:

1. Kyushu University Interdisciplinary Graduate School of Engineering Sciences, Department of Advanced Energy Engineering Science Kasugakouen 6-1, Kasuga, Fukuoka 816-8580, 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/FST02-A200

Reference20 articles.

1. Tritium removal from TFTR

2. Release of hydrogen isotopes from first-wall surfaces on exposure to air

3. Comparison of the thermal stability of the codeposited carbon/hydrogen layer to that of the saturated implant layer

4. In-vessel tritium retention and removal in ITER

5. Tritium retention and clean-up in JET

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1. Location and chemical bond of radionuclides in neutron-irradiated nuclear graphite;Journal of Nuclear Materials;2013-07

2. Hydrogen behavior in Mg+-implanted graphite;Journal of Materials Research;2006-04-01

3. Tritium Release Behavior from JT-60U Vacuum Vessel during Air Exposure Phase and Wall Conditioning Phase;Fusion Science and Technology;2005-08

4. Tritium release behavior from the graphite tiles used at the dome unit of the W-shaped divertor region in JT-60U;Journal of Nuclear Materials;2005-04

5. Isotope exchange reaction between tritiated water and hydrogen on SiC;Journal of Nuclear Materials;2003-11