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Shipping Cask Studies with MOX Fuel.


DE2001786762

Publication Date 2001
Personal Author Pavlovichev, A. M.
Page Count 45
Abstract Tasks of nuclear safety assurance for storage and transport of fresh mixed uranium-plutonium fuel of the VVER-1000 reactor are considered in the new of 3 MOX LTAs introduction into the core. The precise code MCU that realizes the Monte Carlo method is used for calculations.
Keywords
  • Casks
  • Transportation
  • Nuclear fuels
  • Mixed oxide fuels
Source Agency
  • Technical Information Center Oak Ridge Tennessee
Corporate Authors Oak Ridge National Lab., TN.; Department of Energy, Washington, DC.
Document Type Technical Report
NTIS Issue Number 200201
Contract Number
  • AC05-00OR22725
Shipping Cask Studies with MOX Fuel.
Shipping Cask Studies with MOX Fuel.
DE2001786762

  • Casks
  • Transportation
  • Nuclear fuels
  • Mixed oxide fuels
  • Technical Information Center Oak Ridge Tennessee
  • AC05-00OR22725
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