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Criticality safety analysis for a DUPIC fuel cycle facility

Journal Article · · Transactions of the American Nuclear Society
OSTI ID:436920
;  [1]
  1. Kyung Hee Univ., Kyungki-Do (Korea, Democratic People`s Republic of)

The DUPIC fuel cycle option has been studied jointly by Korea Atomic Energy Research Institute, Atomic Energy of Canada Limited, and the U.S. Department of Energy to show its feasibility in engineering, economics, and safeguards. The DUPIC concept is to recycle spent pressurized water reactor (PWR) fuel into a CANDU reactor by dry processes without separating actinides and fission products. The fuel manufacturing facility for DUPIC is no different from a conventional PWR fuel facility except in the following treatments. A whole process should be operated under remote control within a hot cell. This radiation problem can be a bottleneck for commercialization because of mass handling limitations as well as plant size economics. The second issue with DUPIC is the OREOX process, which is the cyclic process of oxidation and reduction of spent PWR pellets. In this process, fine powder should be produced for the compact sintering. Prior to this process, spent fuel assemblies are cooled, disassembled, cut into pieces, and decladded.

OSTI ID:
436920
Report Number(s):
CONF-9606116--
Journal Information:
Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 74; ISSN TANSAO; ISSN 0003-018X
Country of Publication:
United States
Language:
English

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