Evaluation of tritium retention in plasma facing components during JET tritium operations

Anna Widdowson; J. Paul Coad; Yevhen Zayachuk; Ionut Jepu; Eduardo Alves; Norberto Catarino; Victoria Corregidor; Matej Mayer; Stepan Krat; Jari Likonen; Kenichiro Mizohata; Chris Rowley; Miroslaw Zlobinski; Marek Rubel; David Douai; Kalle Heinola; Tom Wauters; Laura Dittrich; Sunwoo Moon; Per Petersson; Aleksandra Baron-Wiechec; Liga Avotina

doi:10.1088/1402-4896/ac3b30

Evaluation of tritium retention in plasma facing components during JET tritium operations

Anna Widdowson (Corresponding Author), J. Paul Coad, Yevhen Zayachuk, Ionut Jepu, Eduardo Alves, Norberto Catarino, Victoria Corregidor, Matej Mayer, Stepan Krat, Jari Likonen, Kenichiro Mizohata, Chris Rowley, Miroslaw Zlobinski, Marek Rubel, David Douai, Kalle Heinola, Tom Wauters, Laura Dittrich, Sunwoo Moon, Per PeterssonAleksandra Baron-Wiechec, Liga Avotina

BA4506 Fusion energy and decommissioning

Research output: Contribution to journal › Article › Scientific › peer-review

2 Citations (Scopus)

Abstract

An assessment of the tritium (T) inventory in plasma facing components (PFC) during JET T and deuterium-tritium (DT) operations is presented based on the most comprehensive ex situ fuel retention data set on JET PFCs from the 2015-2016 ILW3 operating period is presented. The global fuel retention is 4.19 1023 D atoms, 0.19% of injected fuel. The inner divertor remains the region of highest fuel retention (46.5%). The T inventory in PFCs at the end of JET operations is calculated as 7.48 1022 atoms and is informative for accountancy, clean-up efficacy and waste liability assessments. The T accumulation rate at the upper inner divertor during JET DT operations has been used to assess the requirements and frequency of operation of a new laser induced desorption diagnostic to be installed on JET for the final DT experiments in 2023.

Original language	English
Article number	124075
Number of pages	9
Journal	Physica Scripta
Volume	96
Issue number	12
DOIs	https://doi.org/10.1088/1402-4896/ac3b30
Publication status	Published - 15 Dec 2021
MoE publication type	A1 Journal article-refereed

Keywords

fuel retention
JET
tritium

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10.1088/1402-4896/ac3b30Licence: CC BY

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Widdowson, A., Coad, J. P., Zayachuk, Y., Jepu, I., Alves, E., Catarino, N., Corregidor, V., Mayer, M., Krat, S., Likonen, J., Mizohata, K., Rowley, C., Zlobinski, M., Rubel, M., Douai, D., Heinola, K., Wauters, T., Dittrich, L., Moon, S., ... Avotina, L. (2021). Evaluation of tritium retention in plasma facing components during JET tritium operations. Physica Scripta, 96(12), [124075]. https://doi.org/10.1088/1402-4896/ac3b30

Widdowson, Anna ; Coad, J. Paul ; Zayachuk, Yevhen ; Jepu, Ionut ; Alves, Eduardo ; Catarino, Norberto ; Corregidor, Victoria ; Mayer, Matej ; Krat, Stepan ; Likonen, Jari ; Mizohata, Kenichiro ; Rowley, Chris ; Zlobinski, Miroslaw ; Rubel, Marek ; Douai, David ; Heinola, Kalle ; Wauters, Tom ; Dittrich, Laura ; Moon, Sunwoo ; Petersson, Per ; Baron-Wiechec, Aleksandra ; Avotina, Liga. / Evaluation of tritium retention in plasma facing components during JET tritium operations. In: Physica Scripta. 2021 ; Vol. 96, No. 12.

@article{f51062cedf774b9ea06f25f003a20148,

title = "Evaluation of tritium retention in plasma facing components during JET tritium operations",

abstract = "An assessment of the tritium (T) inventory in plasma facing components (PFC) during JET T and deuterium-tritium (DT) operations is presented based on the most comprehensive ex situ fuel retention data set on JET PFCs from the 2015-2016 ILW3 operating period is presented. The global fuel retention is 4.19 1023 D atoms, 0.19% of injected fuel. The inner divertor remains the region of highest fuel retention (46.5%). The T inventory in PFCs at the end of JET operations is calculated as 7.48 1022 atoms and is informative for accountancy, clean-up efficacy and waste liability assessments. The T accumulation rate at the upper inner divertor during JET DT operations has been used to assess the requirements and frequency of operation of a new laser induced desorption diagnostic to be installed on JET for the final DT experiments in 2023. ",

keywords = "fuel retention, JET, tritium",

author = "Anna Widdowson and Coad, {J. Paul} and Yevhen Zayachuk and Ionut Jepu and Eduardo Alves and Norberto Catarino and Victoria Corregidor and Matej Mayer and Stepan Krat and Jari Likonen and Kenichiro Mizohata and Chris Rowley and Miroslaw Zlobinski and Marek Rubel and David Douai and Kalle Heinola and Tom Wauters and Laura Dittrich and Sunwoo Moon and Per Petersson and Aleksandra Baron-Wiechec and Liga Avotina",

note = "Publisher Copyright: {\textcopyright} 2021 The Author(s). Published by IOP Publishing Ltd.",

year = "2021",

month = dec,

day = "15",

doi = "10.1088/1402-4896/ac3b30",

language = "English",

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Widdowson, A, Coad, JP, Zayachuk, Y, Jepu, I, Alves, E, Catarino, N, Corregidor, V, Mayer, M, Krat, S, Likonen, J, Mizohata, K, Rowley, C, Zlobinski, M, Rubel, M, Douai, D, Heinola, K, Wauters, T, Dittrich, L, Moon, S, Petersson, P, Baron-Wiechec, A & Avotina, L 2021, 'Evaluation of tritium retention in plasma facing components during JET tritium operations', Physica Scripta, vol. 96, no. 12, 124075. https://doi.org/10.1088/1402-4896/ac3b30

Evaluation of tritium retention in plasma facing components during JET tritium operations. / Widdowson, Anna (Corresponding Author); Coad, J. Paul; Zayachuk, Yevhen; Jepu, Ionut; Alves, Eduardo; Catarino, Norberto; Corregidor, Victoria; Mayer, Matej; Krat, Stepan; Likonen, Jari; Mizohata, Kenichiro; Rowley, Chris; Zlobinski, Miroslaw; Rubel, Marek; Douai, David; Heinola, Kalle; Wauters, Tom; Dittrich, Laura; Moon, Sunwoo; Petersson, Per; Baron-Wiechec, Aleksandra; Avotina, Liga.

In: Physica Scripta, Vol. 96, No. 12, 124075, 15.12.2021.

Research output: Contribution to journal › Article › Scientific › peer-review

TY - JOUR

T1 - Evaluation of tritium retention in plasma facing components during JET tritium operations

AU - Widdowson, Anna

AU - Coad, J. Paul

AU - Zayachuk, Yevhen

AU - Jepu, Ionut

AU - Alves, Eduardo

AU - Catarino, Norberto

AU - Corregidor, Victoria

AU - Mayer, Matej

AU - Krat, Stepan

AU - Likonen, Jari

AU - Mizohata, Kenichiro

AU - Rowley, Chris

AU - Zlobinski, Miroslaw

AU - Rubel, Marek

AU - Douai, David

AU - Heinola, Kalle

AU - Wauters, Tom

AU - Dittrich, Laura

AU - Moon, Sunwoo

AU - Petersson, Per

AU - Baron-Wiechec, Aleksandra

AU - Avotina, Liga

PY - 2021/12/15

Y1 - 2021/12/15

N2 - An assessment of the tritium (T) inventory in plasma facing components (PFC) during JET T and deuterium-tritium (DT) operations is presented based on the most comprehensive ex situ fuel retention data set on JET PFCs from the 2015-2016 ILW3 operating period is presented. The global fuel retention is 4.19 1023 D atoms, 0.19% of injected fuel. The inner divertor remains the region of highest fuel retention (46.5%). The T inventory in PFCs at the end of JET operations is calculated as 7.48 1022 atoms and is informative for accountancy, clean-up efficacy and waste liability assessments. The T accumulation rate at the upper inner divertor during JET DT operations has been used to assess the requirements and frequency of operation of a new laser induced desorption diagnostic to be installed on JET for the final DT experiments in 2023.

AB - An assessment of the tritium (T) inventory in plasma facing components (PFC) during JET T and deuterium-tritium (DT) operations is presented based on the most comprehensive ex situ fuel retention data set on JET PFCs from the 2015-2016 ILW3 operating period is presented. The global fuel retention is 4.19 1023 D atoms, 0.19% of injected fuel. The inner divertor remains the region of highest fuel retention (46.5%). The T inventory in PFCs at the end of JET operations is calculated as 7.48 1022 atoms and is informative for accountancy, clean-up efficacy and waste liability assessments. The T accumulation rate at the upper inner divertor during JET DT operations has been used to assess the requirements and frequency of operation of a new laser induced desorption diagnostic to be installed on JET for the final DT experiments in 2023.

KW - fuel retention

KW - JET

KW - tritium

UR - http://www.scopus.com/inward/record.url?scp=85123217523&partnerID=8YFLogxK

U2 - 10.1088/1402-4896/ac3b30

DO - 10.1088/1402-4896/ac3b30

M3 - Article

AN - SCOPUS:85123217523

VL - 96

JO - Physica Scripta

JF - Physica Scripta

SN - 0031-8949

IS - 12

M1 - 124075

ER -

Evaluation of tritium retention in plasma facing components during JET tritium operations

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