Thermal desorption spectrometry of beryllium plasma facing tiles exposed in the JET tokamak

Aleksandra Baron-Wiechec; Kalle Heinola; Jari Likonen; Eduardo de Alves; Norberto Catarino; Valeria Corregidor; Paul Coad; Ionut Jepu; Guy Matthews; Anna Widdowson

doi:10.1016/j.fusengdes.2018.05.075

Thermal desorption spectrometry of beryllium plasma facing tiles exposed in the JET tokamak

Aleksandra Baron-Wiechec (Corresponding Author), Kalle Heinola, Jari Likonen, Eduardo de Alves, Norberto Catarino, Valeria Corregidor, Paul Coad, Ionut Jepu, Guy Matthews, Anna Widdowson

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

19 Citations (Scopus)

Abstract

The phenomena of retention and de-trapping of deuterium (D) and tritium (T) in plasma facing components (PFC) and supporting structures must be understood in order to limit or control total T inventory in larger future fusion devices such as ITER, DEMO and commercial machines. The goal of this paper is to present details of the thermal desorption spectrometry (TDS) system applied in total fuel retention assessment of PFC at the Joint European Torus (JET). Examples of TDS results from beryllium (Be) wall tile samples exposed to JET plasma in PFC configuration mirroring the planned ITER PFC is shown for the first time. The method for quantifying D by comparison of results from a sample of known D content was confirmed acceptable. The D inventory calculations obtained from Ion Beam Analysis (IBA) and TDS agree well within an error associated with the extrapolation from very few data points to a large surface area.

Original language	English
Pages (from-to)	135–141
Journal	Fusion Engineering and Design
Volume	133
DOIs	https://doi.org/10.1016/j.fusengdes.2018.05.075
Publication status	Published - 2018
MoE publication type	A1 Journal article-refereed

Funding

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 and from the RCUK Energy Programme [grant number EP/P012450/1]. The views and opinions expressed herein do not necessarily reflect those of the European Commission. The research used UKAEA’s Materials Research Facility, which has been funded by and is part of the UK’s National Nuclear User Facility and Henry Royce Institute for Advanced Materials.

Keywords

Thermal desorption spectrometry
Beryllium
Plasma facing component
Fuel retention
JET
Tritium

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1016/j.fusengdes.2018.05.075

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title = "Thermal desorption spectrometry of beryllium plasma facing tiles exposed in the JET tokamak",

abstract = "The phenomena of retention and de-trapping of deuterium (D) and tritium (T) in plasma facing components (PFC) and supporting structures must be understood in order to limit or control total T inventory in larger future fusion devices such as ITER, DEMO and commercial machines. The goal of this paper is to present details of the thermal desorption spectrometry (TDS) system applied in total fuel retention assessment of PFC at the Joint European Torus (JET). Examples of TDS results from beryllium (Be) wall tile samples exposed to JET plasma in PFC configuration mirroring the planned ITER PFC is shown for the first time. The method for quantifying D by comparison of results from a sample of known D content was confirmed acceptable. The D inventory calculations obtained from Ion Beam Analysis (IBA) and TDS agree well within an error associated with the extrapolation from very few data points to a large surface area.",

keywords = "Thermal desorption spectrometry, Beryllium, Plasma facing component, Fuel retention, JET, Tritium",

author = "Aleksandra Baron-Wiechec and Kalle Heinola and Jari Likonen and {de Alves}, Eduardo and Norberto Catarino and Valeria Corregidor and Paul Coad and Ionut Jepu and Guy Matthews and Anna Widdowson",

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AU - Baron-Wiechec, Aleksandra

AU - Heinola, Kalle

AU - Likonen, Jari

AU - de Alves, Eduardo

AU - Catarino, Norberto

AU - Corregidor, Valeria

AU - Coad, Paul

AU - Jepu, Ionut

AU - Matthews, Guy

AU - Widdowson, Anna

PY - 2018

Y1 - 2018

N2 - The phenomena of retention and de-trapping of deuterium (D) and tritium (T) in plasma facing components (PFC) and supporting structures must be understood in order to limit or control total T inventory in larger future fusion devices such as ITER, DEMO and commercial machines. The goal of this paper is to present details of the thermal desorption spectrometry (TDS) system applied in total fuel retention assessment of PFC at the Joint European Torus (JET). Examples of TDS results from beryllium (Be) wall tile samples exposed to JET plasma in PFC configuration mirroring the planned ITER PFC is shown for the first time. The method for quantifying D by comparison of results from a sample of known D content was confirmed acceptable. The D inventory calculations obtained from Ion Beam Analysis (IBA) and TDS agree well within an error associated with the extrapolation from very few data points to a large surface area.

AB - The phenomena of retention and de-trapping of deuterium (D) and tritium (T) in plasma facing components (PFC) and supporting structures must be understood in order to limit or control total T inventory in larger future fusion devices such as ITER, DEMO and commercial machines. The goal of this paper is to present details of the thermal desorption spectrometry (TDS) system applied in total fuel retention assessment of PFC at the Joint European Torus (JET). Examples of TDS results from beryllium (Be) wall tile samples exposed to JET plasma in PFC configuration mirroring the planned ITER PFC is shown for the first time. The method for quantifying D by comparison of results from a sample of known D content was confirmed acceptable. The D inventory calculations obtained from Ion Beam Analysis (IBA) and TDS agree well within an error associated with the extrapolation from very few data points to a large surface area.

KW - Thermal desorption spectrometry

KW - Beryllium

KW - Plasma facing component

KW - Fuel retention

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KW - Tritium

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JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

ER -

Thermal desorption spectrometry of beryllium plasma facing tiles exposed in the JET tokamak

Abstract

Funding

Keywords

UN SDGs

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