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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.
A. I. Markin, E. A. Azizov, N. I. Siromyatnikov, V. E. Cherkovets, L. A. Rivkis, A. A. Semenov, I. G. Prikina
Fusion Science and Technology | Volume 54 | Number 2 | August 2008 | Pages 489-492
Technical Paper | Materials Interactions | doi.org/10.13182/FST08-A1860
Articles are hosted by Taylor and Francis Online.
The investigations of the tritium distribution in a surface layer and in the depth of samples using a magnetic microscope were carried out. The dependence of a saturation level in the boundary layer for hydrogen was established from a preliminary examination of samples. Conservation of the tritium distribution profile in the depth of the stainless steel samples after completion of their saturation and cooling was assigned. For Inconel-625 substantial tritium redistribution and release during storage (300K, 15 and 28 months) were experimentally ascertained to a greater degree satisfies the classical characteristics of the diffusion process. The "braking" effect of tritium diffusion was found by preliminary saturation of samples by hydrogen. Research in tritium decontamination effects for samples saturated with tritium with various technological preparation was carried out and essential increase of its efficiency was founded. The experiments emulated a model of technological operation cycle of the thermonuclear reactor.