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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Format: | Article |
Language: | English |
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Elsevier
2021-06-01
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Series: | Nuclear Materials and Energy |
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Online Access: | http://www.sciencedirect.com/science/article/pii/S2352179121000740 |
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author | 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 |
author_facet | 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 |
author_sort | Gregory De Temmerman |
collection | DOAJ |
description | 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-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. |
first_indexed | 2024-12-20T01:55:52Z |
format | Article |
id | doaj.art-4ee2b08333664560b3dda94e93de2ef1 |
institution | Directory Open Access Journal |
issn | 2352-1791 |
language | English |
last_indexed | 2024-12-20T01:55:52Z |
publishDate | 2021-06-01 |
publisher | Elsevier |
record_format | Article |
series | Nuclear Materials and Energy |
spelling | doaj.art-4ee2b08333664560b3dda94e93de2ef12022-12-21T19:57:29ZengElsevierNuclear Materials and Energy2352-17912021-06-0127100994Data on erosion and hydrogen fuel retention in Beryllium plasma-facing materialsGregory De Temmerman0Kalle Heinola1Dmitriy Borodin2Sebastijan Brezinsek3Russell P. Doerner4Marek Rubel5Elżbieta Fortuna-Zaleśna6Christian Linsmeier7Daisuke Nishijima8Kai Nordlund9Michael Probst10Juri Romazanov11Elnaz Safi12Thomas Schwarz-Selinger13Anna Widdowson14Bastiaan J. Braams15Hyun-Kyung Chung16Christian Hill17ITER Organisation, Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex, France; Zenon Research, 16 rue Séguier, 75006 Paris, France; MINES ParisTech, Université PSL, Institut des Hautes Etudes pour l’Innovation et l’Entrepreneuriat (IHEIE), 75006 Paris, France; Corresponding author.International Atomic Energy Agency, A-1400, Vienna, AustriaForschungszentrum Jülich GmbH, D-52425, Jülich, GermanyForschungszentrum Jülich GmbH, D-52425, Jülich, GermanyCenter for Energy Research, University of California, San Diego, La Jolla, CA 92093-0417, USAKTH Royal Institute of Technology, SE-1044 Stockholm, SwedenWarsaw University of Technology, 02 507 Warsaw, PolandForschungszentrum Jülich GmbH, D-52425, Jülich, GermanyCenter for Energy Research, University of California, San Diego, La Jolla, CA 92093-0417, USADepartment of Physics, University of Helsinki, P.O. Box 43, 00014 Helsinki, FinlandInstitute for Ion Physics and Applied Physics, University of Innsbruck, 6020 Innsbruck, AustriaForschungszentrum Jülich GmbH, D-52425, Jülich, GermanyDepartment of Physics, University of Helsinki, P.O. Box 43, 00014 Helsinki, FinlandMax-Planck-Institut für Plasmaphysik, Boltzmannstr. 2, 85748 Garching, GermanyCCFE, Culham Science Centre, Abingdon, OX14 3DB, United KingdomInternational Atomic Energy Agency, A-1400, Vienna, Austria; Centrum Wiskunde and Informatica, P.O. Box 94079, 1090 GB, Amsterdam, The NetherlandsInternational Atomic Energy Agency, A-1400, Vienna, Austria; Korea Institute of Fusion Energy, 169-148 Gwahak-ro, Yuseong-gu, Daejon, 34133, Republic of KoreaInternational Atomic Energy Agency, A-1400, Vienna, AustriaITER 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-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.http://www.sciencedirect.com/science/article/pii/S2352179121000740BerylliumControlled fusionPlasma-facing materialErosion–depositionDust |
spellingShingle | 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 Data on erosion and hydrogen fuel retention in Beryllium plasma-facing materials Nuclear Materials and Energy Beryllium Controlled fusion Plasma-facing material Erosion–deposition Dust |
title | Data on erosion and hydrogen fuel retention in Beryllium plasma-facing materials |
title_full | Data on erosion and hydrogen fuel retention in Beryllium plasma-facing materials |
title_fullStr | Data on erosion and hydrogen fuel retention in Beryllium plasma-facing materials |
title_full_unstemmed | Data on erosion and hydrogen fuel retention in Beryllium plasma-facing materials |
title_short | Data on erosion and hydrogen fuel retention in Beryllium plasma-facing materials |
title_sort | data on erosion and hydrogen fuel retention in beryllium plasma facing materials |
topic | Beryllium Controlled fusion Plasma-facing material Erosion–deposition Dust |
url | http://www.sciencedirect.com/science/article/pii/S2352179121000740 |
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