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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.
H. A. Larson, J. I. Sackett
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 223-230
Technical Paper | Instrument | doi.org/10.13182/NT77-A31779
Articles are hosted by Taylor and Francis Online.
An Experimental Breeder Reactor II (EBR-II) anomalous reactivity meter was examined to verify its feasibility as a useful device in a fast reactor system. Anomalous reactivity is calculated by comparing “measured” reactivity with that predicted by system parameters; this provides useful diagnostic, alarm, and possible plant protective functions. Examples include application during an arbitrary rise-to-power for EBR-II as well as effectiveness during an EBR-II loss-of-primary -pumping-power event. Single subassembly flow loss events may be questionable for the crude anomalous reactivity meter described here, but flow disturbances of the magnitude required for this event have been observed with a reactivity meter.