Applicability of β-ray-induced X-ray spectrometry to in situ measurements of
tritium retention in plasma-facing materials in ITER
Fusion Engineering and Design, 81 (2006) 163-168
M. Matsuyamaa, Y. Torikaia, N. Bekrisb, M. Gluglab,
A. Erbec, W. Naegelec, N. Nodad, V. Philippse,
P. Coadf, K. Watanabea
a Hydrogen Isotope Research Center, Toyama University, Gofuku 3190, Toyama 930-8555, Japan
b Tritium Laboratory, FZK, EURATOM Association, D-76021 Karlsruhe, Germany
c Intitute for Materials Research II, FZK, EURATOM Association, D-76021 Karlsruhe, Germany
d National Institute for Fusion Science, Oroshi-cho, Toki-shi, Gifu 509-5292, Japan
e Institute for Plasma Physics, FZJ, EURATOM Association, TEC, 52425 Julich, Germany
f EURATOM/UKAEA Fusion Association, Culham Science Center, Abingdon, Oxon OX14 3DB, UK
Abstract
Applicability of β-ray-induced X-ray spectrometry (BIXS) for in situ measurements of tritium retention by plasma-facing
materials in ITER was examined using two γ-emitters and a divertor tile with metallic supports employed during D-T fusion
experiments in JET. Measurements of the tile with a γ-emitter showed that the presence of the γ-field has no influence in the shape
of the β-ray-induced X-ray spectra, although the whole intensity in the observed energy region was dependent on radioactivity
of the γ-emitters. To simulate more accurately the in-vessel environment of PFMs, one of the divertor tiles with metallic supports
was subjected to BIXS measurements. Although the metallic supports were gamma active, no significant effect was observed on
the recorded X-ray spectrum. These results clearly indicate that BIXS can be applied to in situ measurements of tritium retention
by PFMs with a simple shielding of the X-ray detector.
Keywords: Tritium retention; In situ measurement; BIXS; Plasma-facing materials; ITER