A risk characterization of safety research areas for Integral Fast Reactor program planning Metadata

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  • Main Title A risk characterization of safety research areas for Integral Fast Reactor program planning


  • Author: Mueller, C.J.
    Creator Type: Personal
  • Author: Cahalan, J.E.
    Creator Type: Personal
  • Author: Hill, D.J.
    Creator Type: Personal
  • Author: Kramer, J.M.
    Creator Type: Personal
  • Author: Marchaterre, J.F.
    Creator Type: Personal
  • Author: Pedersen, D.R.
    Creator Type: Personal
  • Author: Sevy, R.H.
    Creator Type: Personal
  • Author: Tilbrook, R.W.
    Creator Type: Personal
  • Author: Wei, T.Y.
    Creator Type: Personal
  • Author: Wright, A.E.
    Creator Type: Personal


  • Name: Argonne National Laboratory
    Place of Publication: Illinois


  • Creation: 1988-01-01


  • English


  • Content Description: This paper characterizes the areas of Integral Fast Reactor (IFR) safety research in terms of their importance in addressing the risk of core disruption sequences for innovative designs. Such sequences have traditionally been determined to constitute the primary risk to public health and safety. All core disruption sequences are folded into four fault categories: classic unprotected (unscrammed) events; loss of decay heat; local fault propagation; and failure of critical reactor structures. Event trees are used to describe these sequences and the areas in the IFR Safety and related Base Technology research programs are discussed with respect to their relevance in addressing the key issues in preventing or delimiting core disruptive sequences. Thus a measure of potential for risk reduction is obtained for guidance in establishing research priorites.
  • Physical Description: Pages: 19


  • Keyword: Research Programs
  • Keyword: Research And Test Reactors
  • Keyword: Reactor Accidents
  • STI Subject Categories: 220600 -- Nuclear Reactor Technology-- Research, Test & Experimental Reactors
  • Keyword: Reactor Shutdown
  • Keyword: Reactor Components
  • STI Subject Categories: 22 General Studies Of Nuclear Reactors
  • Keyword: System Failure Analysis
  • Keyword: Computer Codes
  • Keyword: Fast Reactors
  • STI Subject Categories: 21 Specific Nuclear Reactors And Associated Plants
  • Keyword: S Codes
  • Keyword: Accidents
  • Keyword: Reactors
  • Keyword: Reactor Safety
  • Keyword: Fuel Elements
  • Keyword: Epithermal Reactors
  • Keyword: Design
  • Keyword: Fault Tree Analysis
  • Keyword: Fuel Cans
  • Keyword: Risk Assessment
  • Keyword: After-Heat Removal
  • Keyword: Removal
  • Keyword: Reactor Core Disruption
  • Keyword: Shutdowns
  • STI Subject Categories: 210500 -- Power Reactors, Breeding
  • Keyword: Ifr Reactor
  • Keyword: Systems Analysis
  • Keyword: Safety
  • Keyword: Experimental Reactors
  • Keyword: Zero Power Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety


  • Conference: Safety of next generation power reactors, Seattle, WA, USA, 1 May 1988


  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI


  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Article


  • Text


  • Other: DE88011199
  • Report No.: CONF-880506-17
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 5011170
  • Archival Resource Key: ark:/67531/metadc1055491


  • Display Note: NTIS, PC A03/MF A01; 1.