Retention and release of hydrogen isotopes in tungsten plasma-facing components: the role of grain boundaries and the native oxide layer from a joint experiment-simulation integrated approach-Reference-Cited by-同舟云学术

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Retention and release of hydrogen isotopes in tungsten plasma-facing components: the role of grain boundaries and the native oxide layer from a joint experiment-simulation integrated approach

Published:2017-05-18 Issue:7 Volume:57 Page:076019
ISSN:0029-5515
Container-title:Nuclear Fusion
language:
Short-container-title:Nucl. Fusion

Author:

Hodille E.A.,Ghiorghiu F.,Addab Y.,Založnik A.,Minissale M.,Piazza Z.,Martin C.,Angot T.,Gallais L.,Barthe M.-F.,Becquart C.S.,Markelj S.,Mougenot J.,Grisolia C.,Bisson R.

Funder

A*MIDEX

H2020 Euratom

Publisher

IOP Publishing

Subject

Condensed Matter Physics,Nuclear and High Energy Physics

Link

http://iopscience.iop.org/article/10.1088/1741-4326/aa6d24/pdf

Reference30 articles.

1. Comparison of hydrogen retention in W and W/Ta alloys;Schmid;J. Nucl. Mater.,2012

2. Modelling of hydrogen isotope retention in the tungsten divertor of EAST during ELMy H-mode;Sang;Fusion Eng. Des.,2014

3. Macroscopic rate equation modeling of trapping/detrapping of hydrogen isotopes in tungsten materials;Hodille;J. Nucl. Mater.,2015

4. Deuterium retention in tungsten in dependence of the surface conditions;Ogorodnikova;J. Nucl. Mater.,2003

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1. Cluster dynamics modeling of hydrogen retention and desorption in tungsten with saturation and multi-trapping effect of sinks;Nuclear Fusion;2024-08-12

2. Modelling neutron damage effects on tritium transport in tungsten;Nuclear Fusion;2024-06-24

3. FESTIM: An open-source code for hydrogen transport simulations;International Journal of Hydrogen Energy;2024-04

4. Deuterium uptake, desorption and sputtering from W(110) surface covered with oxygen;Nuclear Fusion;2024-03-05

5. Atomistic modelling of tritium thermodynamics and kinetics in tungsten and its oxides;Nuclear Materials and Energy;2024-03

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