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Options for Multiple Recycling of Reprocessed U in PWR: Technical and Economic Comparison

[+] Author Affiliations
Hubert Druenne, Charles Hardy

Tractebel Engineering S.A., Brussels, Belgium

Paper No. ICONE20-POWER2012-55234, pp. 363-369; 7 pages
doi:10.1115/ICONE20-POWER2012-55234
From:
  • 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference
  • Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes
  • Anaheim, California, USA, July 30–August 3, 2012
  • Conference Sponsors: Nuclear Engineering Division, Power Division
  • ISBN: 978-0-7918-4498-4
  • Copyright © 2012 by ASME

abstract

In a long term management of the nuclear fuel, Pu contained in the spent fuel would be extracted by reprocessing in order to be recycled in PWR or to be stored to feed future GEN IV reactors. U is better recycled in PWR, as long as it is attractive. This paper proposes and compares solutions that allow multiple recycling of U in PWR.

All the solutions are based on blending: either (a) the Enriched Reprocessed U (ERU) assemblies can be reprocessed together with Enriched Natural U (ENU) assemblies and the resulting Reprocessed U (RepU) be re-enriched to produce the next generation ERU, or (b) RepU can be blended with natural U before enrichment of the mixture, or with ENU after its own enrichment. These solutions are compared with each other in terms of achievable equivalence, technical feasibilities and economic efficiency.

Copyright © 2012 by ASME

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