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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.
Raymond K. Maynard, Naphtali M. Mokgalapa, Tushar K. Ghosh, Robert V. Tompson, Dabir S. Viswanath, Sudarshan K. Loyalka
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 429-438
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT11-5
Articles are hosted by Taylor and Francis Online.
The hemispherical total emissivity of Haynes 230, which is regarded as a leading candidate material for heat exchangers in very high temperature reactor (VHTR) systems, was measured with various surface conditions using the ASTM C 835-06 protocol. The emissivity increased from 0.18 at 627 K to 0.235 at 1356 K for Haynes 230 as received sample. The emissivity increased significantly when its surface roughness was increased, or it was oxidized in air, or it was coated with graphite dust, as compared to the as-received material. Higher emissivity has a positive impact on high-temperature reactor operations, particularly for safety, since higher emissivity implies faster decay heat removal in postaccident VHTR environments.