Abstract
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.
| Original language | English |
|---|---|
| Article number | 100994 |
| Journal | Nuclear Materials and Energy |
| Volume | 27 |
| DOIs | |
| State | Published - Jun 2021 |
| Externally published | Yes |
Bibliographical note
Publisher Copyright:© 2021
Funding
This article forms the final report of an IAEA Coordinated Research Project F43020 entitled “Data for Erosion and Tritium Retention in Beryllium Plasma-Facing Materials”. Part of this work has been carried out within the framework of the EUROfusion Consortium and which has received funding from the Euratom research and training program 2014–2018 and 2019–2020 under grant agreement No. 633053 . The views and opinions expressed herein do not necessarily reflect those of the European Commission or of the ITER Organization. Part of this work was supported by a grant from the Department of Energy , DE-FG02-07ER54912 , and as part of the US-EU Bilateral Collaboration on Mixed Materials for ITER . Part of this work received financial support from the tandem accelerator infrastructure by VR-RFI (contract #2017-00646_9 ) and from the Swedish Foundation for Strategic Research (SSF) under contract RIF14-005 . This article forms the final report of an IAEA Coordinated Research Project F43020 entitled ?Data for Erosion and Tritium Retention in Beryllium Plasma-Facing Materials?. Part of this work has been carried out within the framework of the EUROfusion Consortium and which has received funding from the Euratom research and training program 2014?2018 and 2019?2020 under grant agreement No. 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission or of the ITER Organization. Part of this work was supported by a grant from the Department of Energy, DE-FG02-07ER54912, and as part of the US-EU Bilateral Collaboration on Mixed Materials for ITER. Part of this work received financial support from the tandem accelerator infrastructure by VR-RFI (contract #2017-00646_9) and from the Swedish Foundation for Strategic Research (SSF) under contract RIF14-005. DB would like to acknowledge Dmitriy Matveev, Timo Dittmar, Petra Hansen and Rudi Koslowski for their contributions and valuable remarks for the text. The authors declare that they have no known competing financial interests or personal relationships that could have appeared to influence the work reported in this paper.
| Funders | Funder number |
|---|---|
| VR-RFI | 2017-00646_9 |
| U.S. Department of Energy | DE-FG02-07ER54912 |
| Horizon 2020 Framework Programme | 633053 |
| H2020 Euratom | |
| European Commission | |
| Stiftelsen för Strategisk Forskning | RIF14-005 |
| International Atomic Energy Agency |
Keywords
- Beryllium
- Controlled fusion
- Dust
- Erosion–deposition
- Plasma-facing material