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Evaluation of cementation of intermediate level liquid waste produced from fission 99Mo production process and disposal feasibility of cement waste form

  • Shon, Jong-Sik (Radwaste Management Center, Korea Atomic Energy Research Institute) ;
  • Lee, Hyun-Kyu (Radwaste Management Center, Korea Atomic Energy Research Institute) ;
  • Kim, Tack-Jin (Radwaste Management Center, Korea Atomic Energy Research Institute) ;
  • Kim, Gi-Yong (Radwaste Management Center, Korea Atomic Energy Research Institute) ;
  • Jeon, Hongrae (Radwaste Management Center, Korea Atomic Energy Research Institute)
  • Received : 2022.01.04
  • Accepted : 2022.03.24
  • Published : 2022.09.25

Abstract

The Korea Atomic Energy Research Institute (KAERI) is planning the construction of the KIJANG Research Reactor (KJRR) for stable supply of 99Mo. The Fission 99Mo Production Process (FMPP) of KJRR produces solid waste such as spent uranium cake and alumina cake, and liquid waste in the form of intermediate level liquid waste (ILLW) and low level liquid waste (LLLW). This study thus established the operating range and optimum operating conditions for the cementation of ILLW from FMPP. It also evaluated whether cement waste form samples produced under optimum operational conditions satisfy the waste acceptance criteria (WAC) of a disposal facility in Korea (Korea radioactive waste agency, KORAD). Considering economic feasibility and safety, optimum operational conditions were achieved at a w/c ratio of 0.55, and the corresponding salt content was 5.71 wt%. The cement waste form samples prepared under optimum operational conditions were found to satisfy KORAD's WAC when tested for structural stability and leachability. The results indicate that the proposed cementation conditions for the disposal of ILLW from FMMP can be effectively applied to KJRR's disposal facility.

Keywords

Acknowledgement

This work was supported by Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Korea government (MOTIE) (20191510301120, Development of industrial technology & standards for radiological characteristics at a transient phase of permanent shutdown NPPs).

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