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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.
A. Aframian
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 343-349
Technical Paper | Technique | doi.org/10.13182/NT79-A32191
Articles are hosted by Taylor and Francis Online.
Comparative measurements of neutron flux for low-level irradiations in the MOL-∑∑ reactor have been carried out using gold and indium foils and various solid-state nuclear track detectors (SSNTDs) in conjunction with fissile (n,f) and fertile (6Li and 10B) (n,α) converter foils as well as intrinsic detectors. Experimental and computed values of thermal and epithemal neutrons, using 6Li and 10B, are also presented for other arrangements. The results show good agreement and internal consistency for both thermal- and fast-neutron fluences, thus confirming the use of SSNTDs as absolute dosimetric devices.