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Title: Test based reliability assessment method for a safety critical software in reactor protection system - 284

Conference ·
OSTI ID:23035391
; ;  [1];  [2]
  1. Korea Atomic Energy Research Institute 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353(Korea, Republic of)
  2. Ulsan National Institute of Science and Technology UNIST-gil 50, Ulsan 689-798 (Korea, Republic of)

Digitalization of the instrumentation and control systems in nuclear power plant entails some new features which do not exist in analog systems. When the new features are applied in safety critical systems, the risk stemming from them should be quantified properly to assure the reliability of the entire power plant. Among the new features, software is considered as the most important factor because it can cause common cause failure to many redundant systems. Therefore, in this work, a test based reliability assessment method for a safety-critical software is developed. An output of a software is determined by not only inputs but also the internal state of the software at the time. In the case of safety critical software developed for usage in nuclear power plant, it is possible to directly investigate probable internal states thanks to detailed design specification and programing features, and the probable inputs also can be identified based on the physical linearity of each process parameter and hardware characteristics related to data acquisition. In this work, a development method for practical exhaustive test case consisting of investigation of internal state and probable input sets to a specific internal state are suggested. In addition to this, software logic simulator for execution of software logic test and the reliability quantification method based on the test result are developed. The feasibility of the suggested method is demonstrated via a case study. (authors)

Research Organization:
American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI ID:
23035391
Resource Relation:
Conference: NPIC and HIMIT 2017: 10. International Conference on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, San Francisco, CA (United States), 11-15 Jun 2017; Other Information: Country of input: France; 7 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)
Country of Publication:
United States
Language:
English