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Citation |
Paris C, Queral C, Mula J, Gómez-Magán J, Sánchez-Perea M, Meléndez E, Gil J. Reliab. Eng. Syst. Safety 2019; 182: 13-32. |
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Copyright |
(Copyright © 2019, Elsevier Publishing) |
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DOI |
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PMID |
unavailable |
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Abstract |
After the accident at Fukushima Dai-ichi, considerable efforts were put on enhancing the capability of the Nuclear Power Plants to cope with conditions resulting from the loss of plant safety-related systems. The most widespread solution adopted worldwide has been to define and implement new procedures and emergency actuation plans, the so called FLEX strategies. Among these strategies, there are several recovery strategies which involve the use of portable equipment for accomplishing the safety functions of the unavailable systems. In some cases, these strategies have been devised to be performed concurrently to the usual system recovery procedures included in the EOPs of most NPPs. In this regard, the heat sink recovery after the occurrence of a Total Loss of Feedwater (TLFW) in a Westinghouse 3-loop PWR design is a significant example, and it has been chosen in the present study to assess the quantitative risk reduction provided by the usual and FLEX recovery strategies in a Westinghouse 3-loop PWR design. With this aim, the Integrated Safety Assessment (ISA) methodology, developed by the Spanish Nuclear Safety Council (CSN), has been applied to TLFW sequences as part of the collaboration between Technical University of Madrid (UPM), NFQ Solutions and CSN. Language: en |
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Keywords |
, Auxiliary feed water; , Beyond design basis external event; , Critical safety function; , Damage domain; , Damage exceedance frequency; , Damage exceedance probability; , Dynamic event tree; , Emergency operating procedure; , Event tree; , Fault tree; , Feed and bleed; , Full spectrum loss of coolant accident; , Generic event tree; , Generic event tree with uncertainties; , High pressure safety injection; , Initiating event; , Integrated safety assessment; , Loss of coolant accident; , Main feed water; , Spanish nuclear safety council; Damage domain; Dynamic event tree; Integrated safety assessment; Probabilistic safety analysis; Recovery and FLEX strategies |