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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.
R. Saksena, P. Satyamurthy, P. Munshi
Nuclear Technology | Volume 163 | Number 3 | September 2008 | Pages 426-434
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A4000
Articles are hosted by Taylor and Francis Online.
This work focuses on the comparison between the results obtained by gamma-ray tomography (experimental) and the FLUENT code (simulation). The physical property targeted here is the void distribution in the riser leg of a mercury-nitrogen flow system. Multiplicative algebraic reconstruction technique (MART) algorithms have been used for the tomographic image reconstruction. A comparison of the predicted and the experimental results shows that experimental numbers are consistently lower than FLUENT predictions.