Nuclear Engineering and Technology

  • 제53권5호
  • /
  • Pages.1534-1539
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  • 2021
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Dissolution behavior of SrO into molten LiCl for heat reduction in used nuclear fuel

  • Kang, Dokyu (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • Amphlett, James T.M. (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • Choi, Eun-Young (Korea Atomic Energy Research Institute) ;
  • Bae, Sang-Eun (Korea Atomic Energy Research Institute) ;
  • Choi, Sungyeol (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology)
  • 투고 : 2020.08.03
  • 심사 : 2020.11.20
  • 발행 : 2021.05.25
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초록

This study reports on the dissolution behavior of SrO in LiCl at varying SrO concentrations from low concentrations to excess. The amount of SrO dissolved in the molten salt and the species present upon cooling were determined. The thermal behavior of LiCl containing various concentrations of SrO was investigated. The experimental results were compared with results from the simulated results using the HSC Chemistry software package. Although the reaction of SrO with LiCl in the standard state at 650 ℃ has a slightly positive Gibbs free energy, SrO was found to be highly soluble in LiCl. Experimentally determined SrO concentrations were found to be considerably higher than those present in used nuclear fuel (<2 g/kg). As Sr-90 is one of the most important heat-generating nuclides in used nuclear fuel, this finding will be impactful in the development of fast, simple, and proliferation-resistant heat reduction processes for used nuclear fuel without the need for separating nuclear materials. Heat reduction is important as it decreases both the volume necessary for final disposal and the worker handling risk.

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과제정보

This work was supported by the National Research Foundation of Korea (NRF) funded by the Ministry of Science and ICT (The grant number: NRF-2016M2B2B1945249).

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피인용 문헌

  1. Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl3 Molten Salt vol.2021, 2021, https://doi.org/10.1155/2021/9048775