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  3. MELT-I: A SIMPLIFIED MELTDOWN CODE FOR FAST REACTOR SAFETY ANALYSIS.
  1. Home
  2. Publications
  3. MELT-I: A SIMPLIFIED MELTDOWN CODE FOR FAST REACTOR SAFETY ANALYSIS.

MELT-I: A SIMPLIFIED MELTDOWN CODE FOR FAST REACTOR SAFETY ANALYSIS.

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  • 1 January 1968
    • report
    • Published by Office of Scientific and Technical Information (OSTI)
    • https://doi.org/10.2172/4831555
Abstract
The U.S. Department of Energy's Office of Scientific and Technical Information
Keywords
  • N38180* -POWER REACTOR DEVELOPMENT-SAFETY & SITING
  • COMPUTERS
  • DIGITAL SYSTEMS
  • EXCURSIONS
  • FAST NEUTRONS
  • FAST REACTORS
  • FORTRAN
  • HEAT TRANSFER
  • LIQUID METAL COOLANT
  • PROGRAMMING
  • REACTIVITY
  • REACTOR SAFETY
  • REACTORS
  • UNIVAC
  • UNIVAC 1108
  • LIQUID METAL-COOLED/CORE BEHAVIOR IN FAST
  • MELT-1 HEAT TRANSFER-NEUTRONICS COMPUTER PROGRAM FOR MAJOR EXCURSION EFFECTS ON
  • REACTOR SAFETY/CORE HEAT TRANSFER-NEUTRONICS BEHAVIOR IN FAST LIQUID SODIUM- COOLED REACTORS
  • MELT-1 COMPUTER PROGRAM FOR MAJOR EXCURSION EFFECTS ON
  • FAST/CORE BEHAVIOR IN LIQUID SODIUM-COOLED

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