journal article·2006-10

Hydrogen isotope retention of JT-60U W-shaped divertor tiles exposed to DD discharges

T. Shibahara, T. Tanabe, Y. Hirohata, Y. Oya, M. Oyaidzu, A. Yoshikawa, Y. Onishi, T. Arai, K. Masaki, K. Okuno, N. Miya

Journal of Nuclear Materials· Volume 357· Issue 1-3
Publisher page

Abstract

Deuterium (D) and Hydrogen (H) retention in carbon tiles exposed to DD and HH discharges in the JT-60U W-shaped divertor has been investigated by means of thermal desorption spectroscopy (TDS) and secondary ion mass spectrometry (SIMS). In the thick re-deposited layers on the outer divertor, hydrogen (H + D) was retained rather homogeneously with its concentration of 0.03 in (D + H)/C atomic ratio, which is attributed to the surface temperature rise above 900 K. Owing to the HH discharges performed after the DD discharges for tritium removal, H-dominated re-deposited layers were added on D-dominated re-deposited layers. In addition D retained in near surface layers were replaced by H both for re-deposited and eroded area. Accordingly deuterium concentration peaked at a little inside behind the H dominated surface layers for all tiles. The temperature increase during the discharge very likely causes the saturation of hydrogen retention even in the re-deposited layers. Accordingly the global wall saturation was observed in JT-60U.
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OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Nuclear reactor physics and engineering

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