Exhaustive test cases for the software reliability of safety-critical digital systems in nuclear power plants

Author:

Cho Jaehyun,Shin Sung Min,Lee Seung Jun,Jung Wondea

Funder

National Research Foundation of Korea

Ministry of Science, ICT & Future Planning

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference27 articles.

1. Aldemir, T., Miller, D.W., Stovsky, M.P., Kirschenbaum, J., Bucci, P., Fentiman, A.W., Mangan, L.T., 2006. Current State of Reliability Modeling Methodologies for Digital Systems and Their Acceptance Criteria for Nuclear Power Plant Assessments (NUREG/CR-6901), 2-23-2–26. Retrieved from http://pbadupws.nrc.gov/docs/ML0608/ML060800179.pdf.

2. ANSI/IEEE, “Standard Glossary of Software Engineering Terminology”, STD-729-1991, ANSI/IEEE, 1991.

3. Reliability analysis of digital systems in a probabilistic risk analysis for nuclear power plants;Authen;Nucl. Eng. Technol.,2012

4. Fault-weighted quantification method of fault detection coverage through fault mode and effect analysis in digital I&C systems;Cho;Nucl. Eng. Des.,2017

5. Quantification of LOCA core damage frequency based on thermal-hydraulics analysis;Cho;Nucl. Eng. Des.,2017

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