NDLI: Advanced MOX and IMF Fuel Assembly Designs for Multi-Recycling Transuranics

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Zhang, Yunhuang Jean, C. Ragusa
Copyright Year	2010
Abstract	Several new fuel assembly designs for multi-recycling Transuranics from spent nuclear fuel are proposed and investigated. Among these are (1) Mixed Oxide Fuel with Enriched Uranium (MOX-EU), in which Plutonium oxide and U-235 enriched Uranium oxide are mixed (2) MOX fuel with Americium coating, in which a thin layer of Americium is applied to the outer surface of the MOX fuel pellet, and (3) an heterogeneous fuel assembly consists of Inert-Matrix Fuel (IMF) pins at the periphery and UOX pins in the inner zone. All these designs are compatible with standard PWR utilizing 17×17 fuel assemblies. In-reactor fuel depletion simulation and long-term isotopic decay calculation are carried out using DRAGON[1] and ORIGEN[2], separately. Transuranics mass balance and long-term radiotoxicity analyses are implemented and the results are normalized to per 1TWh-electricity produced.
Sponsorship	Nuclear Engineering Division
Starting Page	879
Ending Page	885
Page Count	7
File Format	PDF
ISBN	9780791849309
DOI	10.1115/ICONE18-30153
Volume Number	18th International Conference on Nuclear Engineering: Volume 2
Conference Proceedings	18th International Conference on Nuclear Engineering
Language	English
Publisher Date	2010-05-17
Publisher Place	Xi’an, China
Access Restriction	Subscribed
Subject Keyword	Uranium Simulation Pins (engineering) Spent nuclear fuels Manufacturing Recycling Coating processes Fuels Coatings Pressurized water reactors
Content Type	Text
Resource Type	Article

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