학술논문

PROSPECTIVE POWER-REACTOR FUEL CYCLES BASED ON WATER-FREE REPROCESSING OF SPENT FUEL
Document Type
Academic Journal
Source
Atomic Energy. May 01, 2004 96(5):320-326
Subject
Language
English
ISSN
1063-4258
Abstract
A pyroelectrochemical process for reprocessing spent fuel and fabricating granular oxides UO2, PuO2 or (U, Pu)O2 from chloride melts has been developed at the Scientific-Research Institute of Nuclear Reactors for a prospective nuclear fuel cycle. The basic equipment has been developed. The basic results of a comprehensive study of fuel elements with vibrationally compacted (U, Pu)O2 fuel for fast reactors are presented. The performance of the reactors remains high up to 30% burnup in standard BOR-60 reactor fuel assemblies and 32% burnup in experimental fuel elements. An assessment is made of the effectiveness of the pyroelectrochemical methods and vibrational compaction technology for plutonium utilization.