Tritium retention in plasma facing materials of JET ITER-Like-Wall retrieved from the vacuum vessel in 2012 (ILW1), 2014 (ILW2) and 2016 (ILW3)
Author:
Funder
Horizon 2020 Euratom
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,Materials Science (miscellaneous),Nuclear and High Energy Physics
Reference33 articles.
1. JET ITER-like wall—overview and experimental programme;Matthews;Phys. Scr.,2011
2. Fuel inventory and material migration of JET main chamber plasma facing components compared over three operational periods;Widdowson;Phys. Scr.,2020
3. Thermal desorption of hydrogen isotopes from the JET Be plasma facing components;Avotina;Phys. Scr.,2020
4. The JET ITER-like wall experiment: first results and lessons for ITER;Horton;Fusion Eng. Des.,2013
5. Efficiency of thermal outgassing for tritium retention measurement and removal in ITER;De Temmerman;Nucl. Mater. Energy,2017
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1. Tritium distributions in castellated structures of Be limiter tiles from JET-ITER-like wall experiments;Nuclear Fusion;2023-03-08
2. Study of Structural and Strength Changes in Lithium-Containing Ceramics—Potential Blanket Materials for Nuclear Power, Subjected to High-Dose Proton Irradiation;Materials;2022-08-13
3. Design of online monitoring of wall material corrosion;Materials Express;2022-04-01
4. Tritium in plasma-facing components of JET with the ITER-Like-Wall;Physica Scripta;2021-11-01
5. D retention and material defects probed using Raman microscopy in JET limiter samples and beryllium-based synthesized samples;Physica Scripta;2021-09-27
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