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.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4930-9
PROCEEDINGS PAPER
Advanced MOX and IMF Fuel Assembly Designs for Multi-Recycling Transuranics Available to Purchase
Yunhuang Zhang,
Yunhuang Zhang
Texas A&M University, College Station, TX
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Jean C. Ragusa
Jean C. Ragusa
Texas A&M University, College Station, TX
Search for other works by this author on:
Yunhuang Zhang
Texas A&M University, College Station, TX
Jean C. Ragusa
Texas A&M University, College Station, TX
Paper No:
ICONE18-30153, pp. 879-885; 7 pages
Published Online:
April 8, 2011
Citation
Zhang, Y, & Ragusa, JC. "Advanced MOX and IMF Fuel Assembly Designs for Multi-Recycling Transuranics." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 2. Xi’an, China. May 17–21, 2010. pp. 879-885. ASME. https://doi.org/10.1115/ICONE18-30153
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