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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.
Jinchoon Kim
Nuclear Technology | Volume 44 | Number 2 | July 1979 | Pages 315-321
Technical Paper | Accelerator | doi.org/10.13182/NT79-A32265
Articles are hosted by Taylor and Francis Online.
Calculations are made of 2.5-MeV neutron yields via D-D reactions from various beam line components, including beam targets and a neutralizer gas cell, and of x-ray generation from accelerator columns in deuterium beam injectors of various energies from 40 to 200 keV, with accelerator powers ranging from 2 to 20 MW per beam line. The calculated neutron intensities from the neutral beam injector systems for present and future fusion research are in the range between 1011 and 1013 n/s and warrant biological shielding in most cases, even for low duty cycle operation. X radiation from the accelerator columns becomes a health physics concern only for injectors with energy higher than ∼100 keV.