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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.
Y. Ueda, H. Kashiwagi, M. Fukumoto, Y. Ohtsuka, N. Yoshida
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 85-90
Divertor and High Heat Flux Components | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8881
Articles are hosted by Taylor and Francis Online.
Simultaneous irradiation effects of He on tungsten blistering with hydrogen and carbon mixed ion beam were investigated. It was found that only 0.1% addition of He ions to 1 keV H and C mixed ion beam (C:0.8-1.0%) reduced (at 473 K) or completely suppressed (at 653 K and 723 K) blister formation. In order to obtain more detailed result, two ion sources were used to irradiate tungsten with H and He ions with different energies. In the He energy of 0.6 keV (1.5 keV H&C),significant blistering was observed, while in the He energies of 1.0 keV and 1.5 keV, blister formation was suppressed. These results suggested that a He bubble layer reduced hydrogen diffusion through the layer. A He bubble size and a volume rate were about 1-2 nm and ~2% at 653 K, respectively. To evaluate T retention in the ITER tungsten wall, this effect should be included.