American Nuclear Society
Home

Home / Publications / Journals / Fusion Science and Technology / Volume 67 / Number 2

Tritium Retention in Reduced-Activation Ferritic/Martensitic Steels

Y. Hatano, V. Kh. Alimov, A. V. Spitsyn, N. P. Bobyr, D. I. Cherkez, S. Abe, O. V. Ogorodnikova, N. S. Klimov, B. I. Khripunov, A. V. Golubeva, V. M. Chernov, M. Oyaidzu, T. Yamanishi, M. Matsuyama

Fusion Science and Technology / Volume 67 / Number 2 / March 2015 / Pages 361-364

Proceedings of TRITIUM 2013 / dx.doi.org/10.13182/FST14-T30

First Online Publication:January 19, 2015
Updated:February 27, 2015

The effects of displacement damage, plasma exposure and heat loads on T retention in reduced-activation ferritic/martensitic (RAFM) steels were investigated by exposing the steels to DT gas at 473 K. Despite enormous change in surface morphology, T retention in the heat-loaded specimen was comparable with that in the unloaded specimen. The exposure to plasma resulted in a drastic increase in T retention at the surface and/or sub surface. However, the T trapped at the surface/subsurface was easily removed by maintaining the specimens in air at ∼300 K. Formation of radiation-induced defects led to a significant increase in T retention, and T trapped in the defects was not removed at ∼300 K. These observations suggest that displacement damages have the largest effects on T retention at ∼473 K.