Best estimate analysis of complete loss of normal feedwater without reactor scram for a PWR plant

M. Ragheb, A. Ikonomopoulos, B. G. Jones, S. A. Ho, R. Endicott

Research output: Contribution to conferencePaper

Abstract

This paper presents the results of a complete loss of normal feedwater without reactor scram transient analysis, for the Salem Westinghouse four loop Pressurized Water Reactor. The analysis has been performed using the Best-Estimate code, RELAP5/MOD2 on a Cyber 932 computer under the NOS/VE Operating System. The loss of feedwater is an anticipated transient and is considered as a Condition II event, a Fault of Moderate Frequency as defined by ANSI-N182-1973. Although it has a low probability of occurrence, a complete loss of normal feedwater is here evaluated with the additional assumption that a nonmechanistic, common mode failure prevents the control rods from dropping into the core. This transient is one among others performed for this plant. It is here discussed using a set of parametric analysis. The effort is motivated by the current interest in using best-estimate methodologies to supplement design basis codes and Evaluation Models in Nuclear Utilities environments.

Original languageEnglish (US)
Pages117-122
Number of pages6
StatePublished - Dec 1 1990
EventWinter Annual Meeting of the American Society of Mechanical Engineers - Dallas, TX, USA
Duration: Nov 25 1990Nov 30 1990

Other

OtherWinter Annual Meeting of the American Society of Mechanical Engineers
CityDallas, TX, USA
Period11/25/9011/30/90

ASJC Scopus subject areas

  • Engineering(all)

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    Ragheb, M., Ikonomopoulos, A., Jones, B. G., Ho, S. A., & Endicott, R. (1990). Best estimate analysis of complete loss of normal feedwater without reactor scram for a PWR plant. 117-122. Paper presented at Winter Annual Meeting of the American Society of Mechanical Engineers, Dallas, TX, USA, .