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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.
Sei-Hun Yun et al.
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 373-378
Materials Development & Plasma-Material Interactions | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12383
Articles are hosted by Taylor and Francis Online.
Experiments were conducted to obtain thermo physical properties of ZrCo and ZrCo hydride, which determine heat transfer phenomena in the hydrogen-ZrCo system. Heat capacity, thermal diffusivity and thermal conductivity of ZrCo and ZrCo hydride using Baotou ZrCo (China) are found to have U shaped curvatures with the temperature increase. In the temperature range of 300 - 500 K the thermal conductivity of ZrCoHx was found to be about 2/3 that of ZrCo and the initial hydrogen content of ZrCoHx used in this study was taken to be x=2.0.
