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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.
G. Cao, S. J. Weber, S. O. Martin, T. L. Malaney, S. R. Slattery, M. H. Anderson, K. Sridharan, T. R. Allen
Nuclear Technology | Volume 175 | Number 2 | August 2011 | Pages 460-467
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT11-A12317
Articles are hosted by Taylor and Francis Online.
An experimental facility for in situ measurements of high-temperature spectral emissivity of materials in environments of interest to the gas-cooled very high temperature reactor (VHTR) has been developed. The facility is capable of measuring emissivities of seven materials in a single experiment, thereby enhancing the accuracy in measurements due to even minor systemic variations in temperatures and environments. The system consists of a cylindrical silicon carbide (SiC) block with seven sample cavities and a deep blackbody cavity, a detailed optical system, and a Fourier transform infrared spectrometer. The reliability of the facility has been confirmed by comparing measured spectral emissivities of SiC, boron nitride, and alumina (Al2O3) at 600°C against those reported in literature. The spectral emissivities of two candidate alloys for VHTR, INCONEL® alloy 617 (INCONEL is a registered trademark of the Special Metals Corporation group of companies) and SA508 steel, in air environment at 700°C were measured.