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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.
Luis Hernandez-Adame, Hector Contreras-Sandoval, Hector Rene Vega-Carrillo, Leonel Humberto Perez Landeros
Nuclear Technology | Volume 175 | Number 1 | July 2011 | Pages 105-112
Technical Paper | Special Issue on the 16th Biennial Topical Meeting of the Radiation Protection and Shielding Division / Accelerators | doi.org/10.13182/NT11-A12277
Articles are hosted by Taylor and Francis Online.
This work studies the design of the treatment room for an 18-MV linac to ensure radiation protection and safety of hospital staff and patients. The walls' thickness, the door, and the maze were designed according to the National Council on Radiation Protection and Measurements Report 151 recommendations. The results of this work are contrasted with the Monte Carlo calculations performed with the MCNP5 code where dose equivalents due to neutrons and neutron spectra estimated at different points inside and outside the radiotherapy room verify that the shielding thicknesses obtained are enough to reduce the dose level permitted by Mexican regulation.