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Enhancing Probabilistic Risk Assessment Methodology for Solving Reactor Safety Issues

[+] Author Affiliations
F. L. Cho

RiskSolver Communications – Consultants, Irvine, CA

Paper No. PVP2003-1918, pp. 313-323; 11 pages
doi:10.1115/PVP2003-1918
From:
  • ASME 2003 Pressure Vessels and Piping Conference
  • Computer Technology and Applications
  • Cleveland, Ohio, USA, July 20–24, 2003
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-1699-0
  • Copyright © 2003 by ASME

abstract

This paper reveals a paradigm of analyzing the consequential effects of severe nuclear reactor accident, radionuclides fraction and source terms release, that will influence the MACCS2 codification [1], by coupling with the results of SAPHIA-PSA Levels l & 2 quantification process [2], MELCORE [3], STCP [4], PST [5], and XSOR [6]. Those codes are mutually exclusive and useful. However, it lacks of the closed interface and linkage for addressing Plant Damage States (PDS), Severe Accident Sequences, and Risk Consequence. Thus, it is imperative to formulate the consistent baseline information for MACCS2, PSA Levels 1, 2 and 3, and then linking to a new algorithm of NCM.

Copyright © 2003 by ASME

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