Evaluation of surveillance test interval from risk viewpoint

IEEE Transactions on Nuclear Science

Volumn 45, Issue 3 PART 1, 1998, Pages 1009-1013

  Chou, H P ^a  

^a NATIONAL TSING HUA UNIVERSITY   (Taiwan)

Author keywords

[No Author keywords available]

Indexed keywords

CORE MELTDOWN; ELECTRIC CIRCUIT BREAKERS; ELECTRIC EQUIPMENT PROTECTION; ERRORS; FAILURE ANALYSIS; MATHEMATICAL MODELS; PROBABILITY; RISK ASSESSMENT; SENSITIVITY ANALYSIS; TRANSIENTS;

ANTICIPATED TRANSIENT WITHOUT SCRAM; EVENT TREE ANALYSES; REACTOR PROTECTION SYSTEM; SURVEILLANCE TEST INTERVAL EVALUATION; SURVEILLANCE TEST INTERVAL RELAXATION; UNCERTAINTY;

NUCLEAR POWER PLANTS;

EID: 0032098929     PISSN: 00189499     EISSN: None     Source Type: Journal    
DOI: 10.1109/23.682698     Document Type: Article

References (7)

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2. S.A. Eide and M.B. Galley, "Generic Component Failure Database," International Topical Meeting on Probabilistic Safety Assessment, Idaho Falls, USA (1993).
3. S.A. Eide, S.V. Chielewski, and T.D. Swantz, "Generic Component Failure Data Base for Light Water and liquid Sodium Reactor PRAs," EG&G Idaho Inc., Idaho Falls USA (1990).
4. "IEEE Guide to the Collection and Presentation of Electrical, Electronic, and Sensory Component Reliability Data for Nuclear Power Generating Station," IEEE Standards 500, IEEE/John Wiley and Sons, Inc., New York, N.Y. (1997).
5. C.D. Gentillow, "Component Failure Data Hankbook," EG&G Idaho Inc., Idaho Falls, USA (1991).
6. "Seabrook Station Probabilistic Safety Assessment," Public Service Company of New Hampshire, USA (1983).
7. S. K. Chen, T.J. Lin, and Y.H. Huang, "Final Report for Probabilistic Risk Assessment of Maanshan Nuclear Power Station," Vol. 1 and 2, Atomic Energy Council, Executive Yuan, Republic of China (1995)