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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
J. Chêne, P. Trabuc, O. Gastaldi
Fusion Science and Technology | Volume 54 | Number 2 | August 2008 | Pages 510-514
Technical Paper | Materials Interactions | doi.org/10.13182/FST08-A1865
Articles are hosted by Taylor and Francis Online.
The behavior of hydrogen and its isotopes in materials is a major concern in future nuclear systems both for the predictive analysis of the role of H, D, T in the environmental degradation of structural materials, for the confinement and inventory of tritium, and for the management of tritiated wastes.This study is focused on the characterization of the effect of the alloy microstructure, of desorption anneal and of oxide films on the tritium behavior (desorption kinetics, trapping, residual concentration) in various austenitic stainless steels.Different techniques (high temperature extraction of hydrogen, beta counting of tritium in massive samples) were used to study : the tritium absorption and desorption in several stainless steels, the role of the annealing conditions (temperature/time) on the tritium residual concentration and desorption flow, and the role of microstructural defects and of oxide films on the diffusion and trapping of tritium.