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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. G. Alsmiller, Jr., J. Barish
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 318-321
Technical Note | Material | doi.org/10.13182/NT77-A31794
Articles are hosted by Taylor and Francis Online.
Calculated results are presented of the variation with position in the experimental volume of a Li(D,n) neutron radiation damage facility of the damage energy and helium and hydrogen production in copper and in niobium when this volume is partially filled with experimental samples. At a given position in the experimental volume for either copper or niobium, the ratio of the damaged energy with no absorber to the damaged energy with a 50-mm-thick iron absorber or a 100-mm-thick carbon absorber is never >3 and in most positions is <2. The neutron nonelastic cross-section data at the higher energies (>15 to 20 MeV) needed to carry out the transport calculations were obtained from the intranuclear-cascade model of nuclear reactions.