• Title/Summary/Keyword: Uranium Liquid Radwaste

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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;Lee, Hyun-Kyu;Kim, Tack-Jin;Kim, Gi-Yong;Jeon, Hongrae
    • Nuclear Engineering and Technology
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    • v.54 no.9
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    • pp.3235-3241
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    • 2022
  • 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.

Effect of Surface-Modification of Activated Carbon for Adsorption of Uranium in Radioactive Liquid Wastes (방사성 액체 폐기물 내 우라늄 흡착에 대한 활성탄의 표면 처리 영향)

  • Jang, J.D.;Lee, K.W.;Song, K.C.;Kang, H.;Oh, W.Z.
    • Journal of Korean Society of Environmental Engineers
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    • v.22 no.5
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    • pp.827-835
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    • 2000
  • Adsorption characteristics of uranium on activated carbon whose surface is modified with $HNO_3$ and/or NaOH were investigated. Na-OAC, which was the activated carbon treated with both $HNO_3$ and NaOH. showed higher adsorption capacity than OAC, which was treated with $HNO_3$, as well as Na-AC, which was treated with only NaOH. This can be explained based on the surface functional groups increased by surface modification of activated carbon and the change of solution pH as adsorption proceeds. From these experimental results, it is thought that the pH of uranium solution and surface functional groups on the activated carbon surface are the governing factors in the uranium adsorption system.

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