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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.
J. J. Doroshenko, S. N. Kraitor, T. V. Kuznetsova, K. K. Kushnereva, E. S. Leonov
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 296-304
Technical Paper | Instrument | doi.org/10.13182/NT77-A31791
Articles are hosted by Taylor and Francis Online.
Additional possibilities in achieving high-accuracy measurements of continuous neutron spectra by track and activation detectors have been found. An analysis of energy characteristics of detectors containing 235U in boron filters of different thicknesses shows that they can be used successfully for measuring intermediate neutron spectra. Application of detectors with 231Pa and 236U considerably increases the accuracy of fast-neutron measurements. The problems associated with increasing the accuracy measurements resulted in the necessity of studying a method for minimizing a directed divergence to use it for unfolding the neutron spectra with energy from 0.4 eV to 10 MeV. A suggested variation of the method makes it possible to decrease the influence of experimental errors and composition of the detector set on the spectrum unfolding errors. The neutron spectra were measured at the Vinča, IBR JINR, and IRT-1000 reactors.