Review

  • Journal of Nuclear Fuel Cycle and Waste Technology
  • Volume 7(3); 2009
  • Article

Journal of Nuclear Fuel Cycle and Waste Technology 2009;7(3):167-174. Published online: Sep, 30, 2009

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Assessment of a U Product Purity from Pyroprocessing Spent EBR-Ⅱ Fuel

  • Jung Won Lee ; Han Soo Lee ; Eung Ho Kim ; Jong Hyeon Lee ; D. Vaden ; B. Westpha ; M.F. Simpson
Abstract

A comprehensive analysis has been conducted on the purity of the uranium product generated from a pyroprocessing of EBR-II spent fuel. The analysis results were compared to the low-level waste criteria for both ROK and USA under a collaborativeprogram between INL and KAERI. It is found that the US LLW definition does not include the activity from any U isotopes, but the Korean one does. The analysis results show that Pu-239 is the only alpha emitting isotope other than U isotopes that exceed the limit in the EBR-II U product. Pu contamination of the product seems to be drastically reduced in a preliminary test of the modified cathode process, and the further development of the proposed technology may be possible to meet the US LLW criteria.

Keywords

Pyroprocessing,EBR-II,purity,LLW criteria