A Fuzzy Logic Methodology for Fault-Tree Analysis in Critical Safety Systems
- University of Tennessee, Knoxville, TN (United States)
A new approach for fault-tree analysis in critical safety systems employing fuzzy sets for information representation is presented in this paper. The methodology is based on the utilization of the extension principle for mapping crisp measurements to various degrees of membership in the fuzzy set of linguistic Truth. Criticality alarm systems are used in miscellaneous nuclear fuel processing, handling, and storage facilities to reduce the risk associated with fissile material operations. Fault-tree methodologies are graphic illustrations of tile failure logic associated with the development of a particular system failure (top event) from basic subcomponent failures (primary events). The term event denotes a dynamic change of state that occurs to system elements, which may include hardware, software, human, or environmental factors. A fault-tree represents a detailed, deductive, analysis that requires extensive system information. The knowledge incorporated in a fault tree can be articulated in logical rules of the form "IF A is true THEN B is true." However, it is well known that this type of syllogism fails to give an answer when the satisfaction of the antecedent clause is only partial. Zadeh suggested a new type of fuzzy conditional inference. This type of syllogism (generalized modus ponens) reads as follows: Premise: A is partially true Implication: IF A is true THEN B is true Conclusion: B is partially-true. In generalized modus ponens, the antecedent is true only to some degree; hence, it is desired to compute the grade to which the consequent is satisfied. Fuzzy sets provide a natural environment for this type of computation because fuzzy variables (e.g., B) can take fuzzy values (e.g., partially-true).
- Research Organization:
- Univ. of Tennessee, Knoxville, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 5892679
- Report Number(s):
- CONF-930601-; CODEN: TANSAO
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 68; Conference: American Nuclear Society (ANS) Annual Meeting, San Diego, CA (United States), 20-24 Jun 1993; ISSN 0003-018X
- Publisher:
- American Nuclear Society
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
42 ENGINEERING
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
ALARM SYSTEMS
FUZZY LOGIC
SAFETY ANALYSIS
NUCLEAR FACILITIES
CRITICALITY
FAULT TREE ANALYSIS
SAFETY ENGINEERING
ENGINEERING
MATHEMATICAL LOGIC
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
Nuclear Criticality Safety Program (NCSP)
Fault-Tree Analysis
New Approach
Fuzzy Sets
Information Representation
054000* - Nuclear Fuels- Health & Safety
420203 - Engineering- Handling Equipment & Procedures