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Structural integrity of DEMO divertor target assessed by neutron tomography

Triestino Minniti, Frank Schoofs, Llion Evans Orcid Logo, Winfried Kockelmann, Jeong-Ha You, Heather Lewtas

Fusion Engineering and Design, Volume: 169, Start page: 112661

Swansea University Author: Llion Evans Orcid Logo

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Abstract

The divertor target plates are the most exposed in-vessel components to high heat flux loads in a fusion reactor due to a combination of plasma bombardment, radiation and nuclear heating. Reliable exhaust systems of such a huge thermal power required a robust and durable divertor target with a suffi...

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Published in: Fusion Engineering and Design
ISSN: 0920-3796
Published: Elsevier BV 2021
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URI: https://cronfa.swan.ac.uk/Record/cronfa56948
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first_indexed 2021-05-24T10:10:30Z
last_indexed 2023-01-11T14:36:31Z
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spelling 2022-08-15T15:02:15.4565422 v2 56948 2021-05-24 Structural integrity of DEMO divertor target assessed by neutron tomography 74dc5084c47484922a6e0135ebcb9402 0000-0002-4964-4187 Llion Evans Llion Evans true false 2021-05-24 MECH The divertor target plates are the most exposed in-vessel components to high heat flux loads in a fusion reactor due to a combination of plasma bombardment, radiation and nuclear heating. Reliable exhaust systems of such a huge thermal power required a robust and durable divertor target with a sufficiently large heat removal capability and lifetime. In this context, it is pivotal to develop non-destructive evaluation methods to assess the structural integrity of this component that, if compromised could reduced its lifetime. In this work we have demonstrated for the first time the feasibility of using neutron tomography to detect volumetric defects within DEMO divertor mock-ups with a spatial resolution of the order of hundreds of micrometers. Neutron tomography is applicable for studying complex structures, often manufactured from exotic materials which are not favourable for conventional non-destructive evaluation methods. This technique could be effectively used during research and development cycles of fusion component design or for quality assurance during manufacturing. Journal Article Fusion Engineering and Design 169 112661 Elsevier BV 0920-3796 Divertor target, Tungsten, Monoblock, CuCrZr, Neutron tomography, Non-destructive evaluation, Qualification 1 8 2021 2021-08-01 10.1016/j.fusengdes.2021.112661 COLLEGE NANME Mechanical Engineering COLLEGE CODE MECH Swansea University IMAT (DOI:10.5286/ISIS.E.RB1820093) facility. This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014–2018 under grant agreement No 633053, from the RCUK Energy Programme [grant number EP/I501045] and EPSRC [grant number EP/R012091/1]. 2022-08-15T15:02:15.4565422 2021-05-24T11:09:05.1289233 Faculty of Science and Engineering School of Aerospace, Civil, Electrical, General and Mechanical Engineering - Mechanical Engineering Triestino Minniti 1 Frank Schoofs 2 Llion Evans 0000-0002-4964-4187 3 Winfried Kockelmann 4 Jeong-Ha You 5 Heather Lewtas 6 56948__20016__670bf155f28b4aadbb8d067b89a5bfd0.pdf 56948 (2).pdf 2021-05-27T09:13:49.2259194 Output 7354248 application/pdf Version of Record true Crown Copyright © 2021 This is an open access article under the Open Government License (OGL) true eng http://www.nationalarchives.gov.uk/doc/open-government-licence/version/3/
title Structural integrity of DEMO divertor target assessed by neutron tomography
spellingShingle Structural integrity of DEMO divertor target assessed by neutron tomography
Llion Evans
title_short Structural integrity of DEMO divertor target assessed by neutron tomography
title_full Structural integrity of DEMO divertor target assessed by neutron tomography
title_fullStr Structural integrity of DEMO divertor target assessed by neutron tomography
title_full_unstemmed Structural integrity of DEMO divertor target assessed by neutron tomography
title_sort Structural integrity of DEMO divertor target assessed by neutron tomography
author_id_str_mv 74dc5084c47484922a6e0135ebcb9402
author_id_fullname_str_mv 74dc5084c47484922a6e0135ebcb9402_***_Llion Evans
author Llion Evans
author2 Triestino Minniti
Frank Schoofs
Llion Evans
Winfried Kockelmann
Jeong-Ha You
Heather Lewtas
format Journal article
container_title Fusion Engineering and Design
container_volume 169
container_start_page 112661
publishDate 2021
institution Swansea University
issn 0920-3796
doi_str_mv 10.1016/j.fusengdes.2021.112661
publisher Elsevier BV
college_str Faculty of Science and Engineering
hierarchytype
hierarchy_top_id facultyofscienceandengineering
hierarchy_top_title Faculty of Science and Engineering
hierarchy_parent_id facultyofscienceandengineering
hierarchy_parent_title Faculty of Science and Engineering
department_str School of Aerospace, Civil, Electrical, General and Mechanical Engineering - Mechanical Engineering{{{_:::_}}}Faculty of Science and Engineering{{{_:::_}}}School of Aerospace, Civil, Electrical, General and Mechanical Engineering - Mechanical Engineering
document_store_str 1
active_str 0
description The divertor target plates are the most exposed in-vessel components to high heat flux loads in a fusion reactor due to a combination of plasma bombardment, radiation and nuclear heating. Reliable exhaust systems of such a huge thermal power required a robust and durable divertor target with a sufficiently large heat removal capability and lifetime. In this context, it is pivotal to develop non-destructive evaluation methods to assess the structural integrity of this component that, if compromised could reduced its lifetime. In this work we have demonstrated for the first time the feasibility of using neutron tomography to detect volumetric defects within DEMO divertor mock-ups with a spatial resolution of the order of hundreds of micrometers. Neutron tomography is applicable for studying complex structures, often manufactured from exotic materials which are not favourable for conventional non-destructive evaluation methods. This technique could be effectively used during research and development cycles of fusion component design or for quality assurance during manufacturing.
published_date 2021-08-01T04:12:18Z
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