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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.
Jae-Hyuk Eoh, Ji-Woong Han, Tae-Ho Lee, Seong-O Kim
Nuclear Technology | Volume 170 | Number 2 | May 2010 | Pages 290-305
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT10-A9484
Articles are hosted by Taylor and Francis Online.
To enhance the operational reliability of a purely passive decay heat removal system in KALIMER, which is named PDRC, three design options to prevent sodium freezing in an intermediate decay heat removal circuit were proposed, and their feasibilities have been studied for an entire plant operation mode. The potential candidates for the new design options are (a) the partially immersed DHX concept, (b) the cavity air cooling system-coupled PDRC concept, and (c) the advanced PDRC concept with alternative cooling medium. The design features of each concept are quantitatively evaluated in this study. For all the options, more specific design considerations were made to confirm their feasibility to properly materialize their concepts in a practical system design procedure, and the general definitions for a purely passive concept and its design features have been discussed as well.