Probabilities of inherent shutdown of unprotected events in innovative liquid metal reactors Metadata

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  • Main Title Probabilities of inherent shutdown of unprotected events in innovative liquid metal reactors


  • Author: Mueller, C.J.
    Creator Type: Personal
  • Author: Wade, D.C.
    Creator Type: Personal


  • Name: Argonne National Laboratory
    Place of Publication: Illinois


  • Creation: 1988-01-01


  • English


  • Content Description: The uncertainty in predicting the effectiveness of inherent shutdown in innovative liquid metal cooled reactors with metallic fuel results from three broad contributing areas of uncertainty: (1) the inability to exactly predict the frequency of ATWS events with potential to challenge the safety systems and require inherent shutdown; (2) the approximation of representing all such events by a selected set of ''generic scenarios''; and (3) the inability to exactly calculate the core response to the selected generic scenarios. This paper discusses the work being done to address each of these contributing areas, identifies the design and research approaches being used at Argonne National Laboratory to reducing the key contributions to uncertainties in inherent shutdown, and presents results. The conditional probabilities (given ATWS initiation) of achieving temperatures capable of defeating inherent shutdown are shown to range from /approximately/0.1% to negligible for current designs.
  • Physical Description: Pages: 12


  • Keyword: Reactor Shutdown
  • Keyword: Mathematical Models
  • Keyword: Reactor Protection Systems
  • STI Subject Categories: 22 General Studies Of Nuclear Reactors
  • Keyword: Reactor Accidents
  • Keyword: Fast Reactors
  • STI Subject Categories: 21 Specific Nuclear Reactors And Associated Plants
  • Keyword: Seismic Effects
  • Keyword: Shutdowns 220900* -- Nuclear Reactor Technology-- Reactor Safety
  • Keyword: Lmfbr Type Reactors
  • Keyword: Transients
  • Keyword: Accidents
  • Keyword: Reactors
  • Keyword: Probability
  • Keyword: Reactor Safety
  • Keyword: Management
  • Keyword: Liquid Metal Cooled Reactors
  • Keyword: Epithermal Reactors
  • Keyword: Breeder Reactors
  • Keyword: Loss Of Coolant
  • Keyword: Fbr Type Reactors
  • Keyword: Reactor Core Disruption
  • STI Subject Categories: 210500 -- Power Reactors, Breeding
  • Keyword: Data Base Management
  • Keyword: 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: DE88009946
  • Report No.: CONF-880506-3
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 5017816
  • Archival Resource Key: ark:/67531/metadc1061430


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