TY  - JOUR
AU  - De Temmerman, Gregory
AU  - Heinola, Kalle
AU  - Borodin, Dmitry
AU  - Brezinsek, Sebastijan
AU  - Doerner, Russell P.
AU  - Rubel, Marek
AU  - Fortuna-Zaleśna, Elżbieta
AU  - Linsmeier, Christian
AU  - Nishijima, Daisuke
AU  - Nordlund, Kai
AU  - Probst, Michael
AU  - Romazanov, Juri
AU  - Safi, Elnaz
AU  - Schwarz-Selinger, Thomas
AU  - Widdowson, Anna
AU  - Braams, Bastiaan J.
AU  - Chung, Hyun-Kyung
AU  - Hill, Christian
TI  - Data on erosion and hydrogen fuel retention in Beryllium plasma-facing materials
JO  - Nuclear materials and energy
VL  - 27
SN  - 2352-1791
CY  - Amsterdam [u.a.]
PB  - Elsevier
M1  - FZJ-2022-04016
SP  - 100994 -
PY  - 2021
AB  - ITER will use beryllium as a plasma-facing material in the main chamber, covering a total surface area of about 620 m. 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-relevant conditions with high particle and heat loads. This paper provides a comprehensive report on the state of knowledge of beryllium behaviour under fusion-relevant conditions: the erosion mechanisms and their consequences, beryllium migration in JET, fuel retention and dust generation. The paper reviews basic laboratory studies, advanced computer simulations and experience from laboratory plasma experiments in linear simulators of plasma–wall interactions and in controlled fusion devices using beryllium plasma-facing components. A critical assessment of analytical methods and simulation codes used in beryllium studies is given. The overall objective is to review the existing set of data with a broad literature survey and to identify gaps and research needs to broaden the database for ITER.
LB  - PUB:(DE-HGF)16
UR  - <Go to ISI:>//WOS:000670923000010
DO  - DOI:10.1016/j.nme.2021.100994
UR  - https://juser.fz-juelich.de/record/910643
ER  -