Published March 2004 | Version v1
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A study on quantitative V and V of safety-critical software

Description

Recently practical needs have required quantitative features for the software reliability for Probabilistic Safety Assessment which is one of the important methods being used in assessing the overall safety of nuclear power plant. But the conventional assessment methods of software reliability could not provide enough information for PSA of NPP, therefore current assessments of a digital system which includes safety-critical software usually exclude the software part or use arbitrary values. This paper describes a Bayesian Belief Networks based method that models the rule-based qualitative software assessment method for a practical use and can produce quantitative results for PSA. The framework was constructed by utilizing BBN that can combine the qualitative and quantitative evidence relevant to the reliability of safety-critical software and can infer a conclusion in a formal and a quantitative way. The case study was performed by applying the method for assessing the quality of software requirement specification of safety-critical software that will be embedded in reactor protection system

Availability note (English)

Available from INIS in electronic form; Also available from Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

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Additional details

Publishing Information

Imprint Pagination
86 p.
Report number
KAERI/TR--2668/2004

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
36097783
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
DIGITAL SYSTEMS; NUCLEAR POWER PLANTS; PROBABILITY; REACTOR PROTECTION SYSTEMS; RELIABILITY; SAFETY; SAFETY ANALYSIS
Descriptors DEC
ENGINEERED SAFETY SYSTEMS; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Notes
15 refs, 12 figs, 7 tabs