Prospective Power-Reactor Fuel Cycles Based on Water-Free Reprocessing of Spent Fuel

Autor:	Yu. S. Sokolovskii, A. V. Bychkov, A. A. Maershin, V. A. Tsykanov, O. V. Skiba, A. F. Grachev, M. V. Kormilitsyn
Rok vydání:	2004
Předmět:	Nuclear fuel cycle Nuclear Energy and Engineering Chemistry Nuclear engineering Uranium-233 Radiochemistry Fuel element failure MOX fuel Spent nuclear fuel Burnup Thorium fuel cycle Spent fuel pool
Zdroj:	Atomic Energy. 96:320-326
ISSN:	1063-4258
Popis:	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.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::719827ff72d2a8395989a326374505da https://doi.org/10.1023/b:aten.0000038097.00145.41 Zobrazit plný text záznamu Full text from SpringerLink