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2024 (Engelska)Ingår i: Nuclear engineering and technology : an international journal of the Korean Nuclear Society, ISSN 1738-5733, E-ISSN 2234-358X, Vol. 56, nr 2, s. 526-535Artikel i tidskrift (Refereegranskat) Published
Abstract [en]
This paper proposes a safety-critical standby component unavailability model that contains aging effects caused by the elapsed time from installation, component degradation due to surveillance tests, and imperfect maintenance actions. An application of the model to a Motor-Operated Valve and a Motor-Driven Pump involved in the HPIS of a VVER/1000-V446 nuclear power plant is demonstrated and compared with other existing models at component and system levels. In addition, the effects of different unavailability models are reflected in the NPP's risk criterion, i.e., core damage frequency, over five maintenance periods. The results show that, compared with other models that do not simultaneously consider the full effects of degradation and maintenance impacts, the proposed model realistically evaluates the unavailabilities of the safety-related components and the involved systems as a plant age function. Therefore, it can effectively reflect the age-dependent CDF impact of a given testing and maintenance policy in a specified time horizon.
Ort, förlag, år, upplaga, sidor
Elsevier, 2024
Nyckelord
Age-dependent unavailability, Imperfect maintenance, Probabilistic safety assessment (PSA), Standby-related failure rate, Test-caused degradation
Nationell ämneskategori
Annan samhällsbyggnadsteknik
Forskningsämne
Drift och underhållsteknik
Identifikatorer
urn:nbn:se:ltu:diva-102428 (URN)10.1016/j.net.2023.10.029 (DOI)001167979000001 ()2-s2.0-85175659005 (Scopus ID)
Anmärkning
Validerad;2024;Nivå 2;2024-03-27 (hanlid);
Full text license: CC BY 4.0
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