Dissolution Behavior of SrO into Molten LiCl for Heat Reduction in Used Nuclear Fuel

' Dissolution Behavior of SrO into Molten LiCl for Heat Reduction in Used Nuclear Fuel' 의 주제별 논문영향력
논문영향력 선정 방법
논문영향력 요약
주제
  • Fission products
  • Heat reduction process
  • Solubility
  • molten-salt
  • pyroprocessing
동일주제 총논문수 논문피인용 총횟수 주제별 논문영향력의 평균
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' Dissolution Behavior of SrO into Molten LiCl for Heat Reduction in Used Nuclear Fuel' 의 참고문헌

  • Underpotential deposition of Li in a molten LiCleLi2O electrolyte for the electrochemical reduction of U from uranium oxides
    J. -M. Hur [2010]
  • Treatment OF oxide spent fuel using the lithium reduction process
  • Thermodynamic Calculations on the Chemical Behavior of SrO During Electrolytic Oxide Reduction
    전민구 [2020]
  • Thermal Analyses of Spent Nuclear Fuel Repository Thermal Analyses of Spent Nuclear Fuel Repository
    K. Ikonen [2003]
  • Solubility of Li[sub 2]O in Molten LiCl–MCl[sub x] (M=Na, K, Cs, Ca, Sr, or Ba) Binary Systems
  • Solubility measurement of Li2O in LiCl molten salt for electro-reduction process
    D. H. Kim [2013]
  • Separations and transmutation criteria to improve utilization of a geologic repository
  • Separation and recovery of uranium metal from spent light water reactor fuel via electrolytic reduction and electrorefining
  • SEPARATION OF STRONTIUM AND CESIUM FROM TERNARY AND QUATERNARY LITHIUM CHLORIDE-POTASSIUM CHLORIDE SALTS VIA MELT CRYSTALLIZATION
  • Preliminary conceptual design and cost estimation for Korea advanced pyroprocessing facility plus(KAPFþ)
    W. Il Ko [2014]
  • Performance modeling and analysis of spent nuclear fuel recycling
    R. Gao [2015]
  • On metal oxide solubilities in some molten alkali metal bromides at T ¼ 973 K
  • On barium oxide solubility in barium-containing chloride melts
  • Interaction of strontium oxide with Sr-Cl2-MCl melts
  • Interaction between barium oxide and barium containing chloride melt
  • Environmental life cycle risk modeling of nuclear waste recycling systems
    S. Choi [2016]
  • Environmental assessment of advanced partitioning, transmutation, and disposal based on long-term risk-informed regulation: PyroGreen
  • Electrolytic reduction of spent nuclear oxide fuel as part of an integral process to separate and recover actinides from fission products
  • Electrolytic reduction of spent light water reactor fuel bench-scale experiment results
    S. Herrmann [2007]
  • Electrolytic reduction of a simulated oxide spent fuel and the fates of representative elements in a Li2O-LiCl molten salt
    W. Park [2016]
  • Electrochemical processing of spent nuclear fuels : an overview of oxide reduction in pyroprocessing technology
    E. Y. Choi [2015]
  • Dynamic assessments on high-level waste and low-and intermediate-level waste generation from open and closed nuclear fuel cycles in Republic of Korea
    S. Choi [2014]
  • Determination of oxide ion activity in molten LiCl using oxide ion electrode
    J. Jeon [2002]
  • Current status of pyroprocessing development at KAERI
    H. Lee [2013]
  • Concentrations of CsCl and SrCl2 from a simulated LiCl salt waste generated by pyroprocessing by using czochralski method
    H. S. Lee [2009]
  • Chapter 3 equilibria in “solid oxide-ionic melt” systems, compr
  • An Experimental Study on an Electrochemical Reduction of an Oxide Mixture in the Advanced Spent-Fuel Conditioning Process
    정상문 [2010]