NDLI: Research of Features of U-Pu-Th Fuel Cycle and its Use for Burning Up of Minor Actinides in Supercritical Water-Cooled Reactor With Fast Neutron Spectrum

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Alexander, P. Glebov Alexey, V. Klushin Yuriy, D. Baranaev Pavel, L. Kirillov
Copyright Year	2013
Abstract	Since 2006 year FSUE “SSC RF – IPPE” and OKB “Gidropress” are being collaborated on a project of a direct cycle reactor cooled by water of supercritical parameters. The vessel type reactor concept with a fast resonance neutron spectrum and a two-pass coolant flow scheme has been chosen as the basic version. Here analysis of fuel cycles for this reactor which MOX (U-Pu)-based fuel consists of WWER spent nuclear fuel and weapon plutonium is presented. Besides, effect of using of thorium and fuel assemblies without a sheath tube is investigated. The following two test tasks are calculated: 1) burning up of isotopes including minor actinides (Am and Cm), 2) nonuniformity of power density distribution on fuel pins. Two approaches such as the WIMS ACADEM program complex developed by IPPE and the Monte-Carlo based program are applied for these tasks.
Sponsorship	Nuclear Engineering Division
File Format	PDF
ISBN	9780791855799
DOI	10.1115/ICONE21-16888
Volume Number	Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors
Conference Proceedings	2013 21st International Conference on Nuclear Engineering
Language	English
Publisher Date	2013-07-29
Publisher Place	Chengdu, China
Access Restriction	Subscribed
Subject Keyword	Water Power density Cycles Vessels Neutrons Pins (engineering) Spent nuclear fuels Combustion Fuels Flow (dynamics) Weapons Nuclear fuel cycle Coolants Resonance Isotopes
Content Type	Text
Resource Type	Article

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