연구동향 분석

Monte Carlo simulations of criticality safety assessments of transuranic element storage in a pyroprocess facility

김진환 김지수 임경택 안성규 박세환 조규성 2018년

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' Monte Carlo simulations of criticality safety assessments of transuranic element storage in a pyroprocess facility' 의 참고문헌

  • Use of curium spontaneous fission neutrons for safeguardability of remotely-handled nuclear facilities: Fuel fabrication in pyroprocessing
  • Use of curium neutron flux from head-end pyroprocessing subsystems for the High Reliability Safeguards methodology
  • Shielding calculation and criticality safety analysis of spent fuel transportation cask in research reactors
  • Review calculations for the OECD/NEA Burn-up Credit Criticality Safety Benchmark
  • Preliminary Safety Study of Engineering-scale Pyroprocess Facility
    문성인 [2014]
  • OrigenArp primer : How to Perform Isotopic Depletion and Decay Calculations with SCALE/ORIGEN
    S.M. Bowman [2010]
  • Nuclear criticality safety considerations in design of dry fuel assembly storage arrays
  • IDENTIFICATION OF SAFETY CONTROLS FOR ENGINEERING-SCALE PYROPROCESS FACILITY
    문성인 [2015]
  • Functional components for a design strategy: Hot cell shielding in the high reliability safeguards methodology
  • Effect of a dual-purpose cask payload increment of spent fuel assemblies from VVER 1000 Bushehr Nuclear Power Plant on basket criticality
    M. Rezaeian [2017]
  • Criticality Calculations with MCNP5 TM : A Primer
    R. Brewer [2009]
  • Application of Safeguards-by-design for the Pyroprocessing Facilities in ROK
    H.D. Kim [2012]
  • Actinide-only and full burn-up credit in criticality assessment of RBMK-1500 spent nuclear fuel storage cask using axial burn-up profile
  • A Review of Best Practices for Monte Carlo Criticality Calculations
    F. Brown [2009]