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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.
Hirofumi Nakamura, Kanetsugu Isobe, Masaru Nakamichi
Fusion Science and Technology | Volume 54 | Number 2 | August 2008 | Pages 341-345
Technical Paper | Tritium in Fission | doi.org/10.13182/FST08-A1827
Articles are hosted by Taylor and Francis Online.
A research program to control tritium in supercritical CO2 (SC-CO2) gas-cooled reactors is presented. This type of reactor is attractive because it offers higher thermal efficiency and lower reactivity with the primary coolant. This program consists of two activities; development of tritium permeation barriers in the heat exchanger tubes and development of tritium removal method from the SC-CO2. For permeation reduction, a glassy coating was developed as the tritium permeation barrier for the SC-CO2 system. Experimental results showed the physical and chemical integrity of the coating for 100 hours soaking in the SCCO2. Significant permeation reduction of 1/20 to 1/60 are obtained. But, further permeation reduction is desired through a new coating technique development, since the permeation reduction at lower temperatures is small.