RELAP5/MOD3.3 Best Estimate Analyses for Human Reliability Analysis

To estimate the success criteria time windows of operator actions the conservative approach was used in the conventional probabilistic safety assessment (PSA). The current PSA standard recommends the use of best-estimate codes. The purpose of the study was to estimate the operator action success cri...

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Main Authors: Andrej Prošek, Borut Mavko
Format: Article
Language:English
Published: Wiley 2010-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2010/797193
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author Andrej Prošek
Borut Mavko
author_facet Andrej Prošek
Borut Mavko
author_sort Andrej Prošek
collection DOAJ
description To estimate the success criteria time windows of operator actions the conservative approach was used in the conventional probabilistic safety assessment (PSA). The current PSA standard recommends the use of best-estimate codes. The purpose of the study was to estimate the operator action success criteria time windows in scenarios in which the human actions are supplement to safety systems actuations, needed for updated human reliability analysis (HRA). For calculations the RELAP5/MOD3.3 best estimate thermal-hydraulic computer code and the qualified RELAP5 input model representing a two-loop pressurized water reactor, Westinghouse type, were used. The results of deterministic safety analysis were examined what is the latest time to perform the operator action and still satisfy the safety criteria. The results showed that uncertainty analysis of realistic calculation in general is not needed for human reliability analysis when additional time is available and/or the event is not significant contributor to the risk.
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series Science and Technology of Nuclear Installations
spelling doaj-art-a9fe18ecb2a64f5eab5eaed275a4c8f12025-02-03T01:11:10ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832010-01-01201010.1155/2010/797193797193RELAP5/MOD3.3 Best Estimate Analyses for Human Reliability AnalysisAndrej Prošek0Borut Mavko1Reactor Engineering Division, Jožef Stefan Institute, Jamova cesta 39, 1000 Ljubljana, SloveniaReactor Engineering Division, Jožef Stefan Institute, Jamova cesta 39, 1000 Ljubljana, SloveniaTo estimate the success criteria time windows of operator actions the conservative approach was used in the conventional probabilistic safety assessment (PSA). The current PSA standard recommends the use of best-estimate codes. The purpose of the study was to estimate the operator action success criteria time windows in scenarios in which the human actions are supplement to safety systems actuations, needed for updated human reliability analysis (HRA). For calculations the RELAP5/MOD3.3 best estimate thermal-hydraulic computer code and the qualified RELAP5 input model representing a two-loop pressurized water reactor, Westinghouse type, were used. The results of deterministic safety analysis were examined what is the latest time to perform the operator action and still satisfy the safety criteria. The results showed that uncertainty analysis of realistic calculation in general is not needed for human reliability analysis when additional time is available and/or the event is not significant contributor to the risk.http://dx.doi.org/10.1155/2010/797193
spellingShingle Andrej Prošek
Borut Mavko
RELAP5/MOD3.3 Best Estimate Analyses for Human Reliability Analysis
Science and Technology of Nuclear Installations
title RELAP5/MOD3.3 Best Estimate Analyses for Human Reliability Analysis
title_full RELAP5/MOD3.3 Best Estimate Analyses for Human Reliability Analysis
title_fullStr RELAP5/MOD3.3 Best Estimate Analyses for Human Reliability Analysis
title_full_unstemmed RELAP5/MOD3.3 Best Estimate Analyses for Human Reliability Analysis
title_short RELAP5/MOD3.3 Best Estimate Analyses for Human Reliability Analysis
title_sort relap5 mod3 3 best estimate analyses for human reliability analysis
url http://dx.doi.org/10.1155/2010/797193
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