Fault tree construction of hybrid system requirements using qualitative formal method
Creators
- 1. Instrumentation and Control, Human Factors Division, Korea Atomic Energy Research Institute, 150, Duckjin-dong, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)
- 2. Computer Science Division, EECS Department and Advanced Information Technology Research Center (AITrc), Korea Advanced Institute of Science and Technology, 373-1, Kusong-dong, Yuseong-gu, Daejeon 305-701 (Korea, Republic of)
Description
When specifying requirements for software controlling hybrid systems and conducting safety analysis, engineers experience that requirements are often known only in qualitative terms and that existing fault tree analysis techniques provide little guidance on formulating and evaluating potential failure modes. In this paper, we propose Causal Requirements Safety Analysis (CRSA) as a technique to qualitatively evaluate causal relationship between software faults and physical hazards. This technique, extending qualitative formal method process and utilizing information captured in the state trajectory, provides specific guidelines on how to identify failure modes and relationship among them. Using a simplified electrical power system as an example, we describe step-by-step procedures of conducting CRSA. Our experience of applying CRSA to perform fault tree analysis on requirements for the Wolsong nuclear power plant shutdown system indicates that CRSA is an effective technique in assisting safety engineers
Additional details
Identifiers
- DOI
- 10.1016/j.ress.2004.04.012;
- PII
- S0951-8320(04)00108-5;
Publishing Information
- Journal Title
- Reliability Engineering and System Safety
- Journal Volume
- 87
- Journal Issue
- 1
- Journal Page Range
- p. 121-131
- ISSN
- 0951-8320
- CODEN
- RESSEP
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36074294
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTERIZED CONTROL SYSTEMS; FAILURE MODE ANALYSIS; FAULT TREE ANALYSIS; HAZARDS; HYBRID SYSTEMS; REACTOR SAFETY; REACTOR SHUTDOWN; SAFETY ANALYSIS; SCRAM; WOLSUNG-1 REACTOR
- Descriptors DEC
- CANDU TYPE REACTORS; CONTROL SYSTEMS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; ON-LINE CONTROL SYSTEMS; ON-LINE SYSTEMS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR SHUTDOWN; REACTORS; SAFETY; SHUTDOWN; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS
Optional Information
- Copyright
- Copyright (c) 2004 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.