File Download

  • Find it @ UNIST can give you direct access to the published full text of this article. (UNISTARs only)
Related Researcher

이승준

Lee, Seung Jun
Nuclear Safety Assessment and Plant HMI Evolution Lab.
Read More

Views & Downloads

Detailed Information

Cited time in webofscience Cited time in scopus
Metadata Downloads

Experimental approach to evaluate software reliability in hardware-software integrated environment

Author(s)
Seo, JeongilKang, Hyun GookLee, Eun-ChanLee, Seung Jun
Issued Date
2020-07
DOI
10.1016/j.net.2020.01.004
URI
https://scholarworks.unist.ac.kr/handle/201301/32308
Fulltext
https://www.sciencedirect.com/science/article/pii/S1738573319306242?via%3Dihub
Citation
NUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.7, pp.1462 - 1470
Abstract
Reliability in safety-critical systems and equipment is of vital importance, so the probabilistic safety assessment (PSA) has been widely used for many years in the nuclear industry to address reliability in a quantitative manner. As many nuclear power plants (NPPs) become digitalized, evaluating the reliability of safety-critical software has become an emerging issue. Due to a lack of available methods, in many conventional PSA models only hardware reliability is addressed with the assumption that software reliability is perfect or very high compared to hardware reliability. This study focused on developing a new method of safety-critical software reliability quantification, derived from hardware-software integrated environment testing. Since the complexity of hardware and software interaction makes the possible number of test cases for exhaustive testing well beyond a practically achievable range, an importance-oriented testing method that assures the most efficient test coverage was developed. Application to the test of an actual NPP reactor protection system demonstrated the applicability of the developed method and provided insight into complex software-based system reliability. (C) 2020 Korean Nuclear Society, Published by Elsevier Korea LLC.
Publisher
KOREAN NUCLEAR SOC
ISSN
1738-5733
Keyword (Author)
Software reliabilityFailure modes and effects analysisDigital instrumentation and controlProbabilistic safety assessment
Keyword
SAFETYSYSTEMS

qrcode

Items in Repository are protected by copyright, with all rights reserved, unless otherwise indicated.