Finite element analysis of hydrogen retention in ITER plasma facing components using FESTIM
Author:
Funder
Euratom Research and Training Programme
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,Materials Science (miscellaneous),Nuclear and High Energy Physics
Reference38 articles.
1. Estimation of the tritium retention in ITER tungsten divertor target using macroscopic rate equations simulations;Hodille;Physica Scripta,2017
2. Efficiency of thermal outgassing for tritium retention measurement and removal in iter;Temmerman;Nucl. Mater. Energy,2017
3. Response of tungsten surfaces to helium and hydrogen plasma exposure under ITER relevant steady state and repetitive transient conditions;Buzi;Nuclear Fusion,2017
4. Thermal conductivity reduction of tungsten plasma facing material due to helium plasma irradiation in pisces using the improved 3-omega method;Cui;J. Nucl. Mater.,2017
5. Degradation of thermal conductivity of the damaged layer of tungsten irradiated by helium-plasma;Qu;Fusion Eng. Des.,2018
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