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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.
T. Kawano, T. Yamano, K. Yamada, M. Tanaka, Y. Asakura, T. Uda
Fusion Science and Technology | Volume 54 | Number 1 | July 2008 | Pages 189-192
Technical Paper | Tritium Measurement | doi.org/10.13182/FST08-A1793
Articles are hosted by Taylor and Francis Online.
A tritium gas monitor was developed by applying several techniques including pulse shape analysis. The optimum analyzer values were determined for parameters such as the bias (voltage) applied to the detector, counting gas flow rate, and mixing ratio of sample air to counting gas using an enclosed tritium reference source. After applying these optimized parameters, the factor for converting counting rate to tritium concentration was determined by conducting an experiment using tritiated methane gas. Finally, the detection limit of the monitor for air samples containing tritium was determined based on the conversion factor.