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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. L. Stakebake, H. N. Robinson
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 30-39
Technical Paper | Reactor | doi.org/10.13182/NT77-A31761
Articles are hosted by Taylor and Francis Online.
The release of PuO2 from plutonium-contaminated burning sodium and liquid sodium under a nitrogen atmosphere has been measured. Also investigated was the release of β-Na4PuO5 from burning sodium. Plutonium concentrations in the initial sodium pool ranged from 13 to 250 ppm. Plutonium dioxide concentrations in the aerosol released from the burning sodium ranged from 5.6 to 1360 ppb. The PuO2 released along with the sodium metal, when the sodium pool was heated in nitrogen at 540°C, varied from 67 to 3632 ppb. The release of β-Na4PuO5 from burning sodium was very small and could only be detected using nuclear track techniques and extended alpha counting. Aerosol particles followed a log-normal particle size distribution. The count mean diameter was 0.48 µm for PuO2 and 0.98 µm for Na2Ox.