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

TY - JOUR

T1 - Thermal desorption spectrometry of beryllium plasma facing tiles exposed in the JET tokamak

AU - JET contributors

AU - Baron-Wiechec, A.

AU - Heinola, K.

AU - Likonen, J.

AU - Alves, E.

AU - Catarino, N.

AU - Coad, J. P.

AU - Corregidor, V.

AU - Jepu, I.

AU - Matthews, G. F.

AU - Widdowson, A.

N1 - Publisher Copyright: © 2018

PY - 2018/8

Y1 - 2018/8

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 - Beryllium

KW - Fuel retention

KW - JET

KW - Plasma facing component

KW - Thermal desorption spectrometry

KW - Tritium

UR - http://www.scopus.com/inward/record.url?scp=85048276128&partnerID=8YFLogxK

U2 - 10.1016/j.fusengdes.2018.05.075

DO - 10.1016/j.fusengdes.2018.05.075

M3 - 文章

AN - SCOPUS:85048276128

SN - 0920-3796

VL - 133

SP - 135

EP - 141

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

ER -