Data on erosion and hydrogen fuel retention in Beryllium plasma-facing materials

Data on erosion and hydrogen fuel retention in Beryllium plasma-facing materials

ITER will use beryllium as a plasma-facing material in the main chamber, covering a total surface area of about 620 m2. Given the importance of beryllium erosion and co-deposition for tritium retention in ITER, significant efforts have been made to understand the behaviour of beryllium under fusion-...

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Bibliographic Details
Main Authors: Gregory De Temmerman, Kalle Heinola, Dmitriy Borodin, Sebastijan Brezinsek, Russell P. Doerner, Marek Rubel, Elżbieta Fortuna-Zaleśna, Christian Linsmeier, Daisuke Nishijima, Kai Nordlund, Michael Probst, Juri Romazanov, Elnaz Safi, Thomas Schwarz-Selinger, Anna Widdowson, Bastiaan J. Braams, Hyun-Kyung Chung, Christian Hill
Format: Article
Language:English
Published: Elsevier 2021-06-01
Series:Nuclear Materials and Energy
Subjects:
Beryllium
Controlled fusion
Plasma-facing material
Erosion–deposition
Dust
Online Access:http://www.sciencedirect.com/science/article/pii/S2352179121000740

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http://www.sciencedirect.com/science/article/pii/S2352179121000740

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