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Conference Paper: Intelligent damage mitigation for BWR nuclear reactors

TitleIntelligent damage mitigation for BWR nuclear reactors
Authors
Issue Date2014
PublisherCRC Press.
Citation
The 11th International Conference on Structural Safety and Reliability (ICOSSAR 2013), Columbia University, New York, NY., 16-20 June 2013. In Safety, Reliability, Risk and Life-Cycle Performance of Structures and Infrastructures, 2013, chapter 611, p. 4563–4568 How to Cite?
AbstractThis paper deals with light water reactor, particularly BWR type nuclear power plants, similar to Fukushima Dai-ichi Nuclear Power Plant with reactors equally vulnerable to core-melt accidents. It first re-iterates the observations and assertions made by Shinozuka (Shinozuka 2012) to recognize that the core-melt is the most critical damage event that must be mitigated by aggressive mitigation procedures if it cannot be prevented. In this regard, it is noteworthy to observe that U.S. Nuclear Energy Institute (NEI) recently intro-duced a procedure FLEX (NEI 2012) for emergency preparedness. This paper however proposes a different procedure as promoted by Shinozuka earlier (Shinozuka 2012) which is now named “Direct Core Cooling System” (DCCS). DCCS is developed making use of mobile closed-circuit water chilling system in such a way that pumps, a part of this system, are (1) directly connected by pipes to the core, (2) while minimizing their connections with any other reactor components. (1) and (2) above indicate the care that must be exer-cised not to get trapped by 3 pitfalls related to such connections. Any one of these pitfalls if trapped can com-promise effectiveness of DCCS. The mobile water chilling system is originally introduced to similar line of research by Cheung (Cheung 1991 & 2012). The cooling action by DCCS takes place as soon as intelligent sensors in the sense of engineering cybernetics detect initial sign of core-melt, and contain the core-melt lead-ing it to a cold shut down.
DescriptionChapter 611
Persistent Identifierhttp://hdl.handle.net/10722/201164
ISBN

 

DC FieldValueLanguage
dc.contributor.authorShinozuka, Men_US
dc.contributor.authorCheung, KPen_US
dc.contributor.authorNifuku, Ten_US
dc.date.accessioned2014-08-21T07:16:13Z-
dc.date.available2014-08-21T07:16:13Z-
dc.date.issued2014en_US
dc.identifier.citationThe 11th International Conference on Structural Safety and Reliability (ICOSSAR 2013), Columbia University, New York, NY., 16-20 June 2013. In Safety, Reliability, Risk and Life-Cycle Performance of Structures and Infrastructures, 2013, chapter 611, p. 4563–4568en_US
dc.identifier.isbn978-1-138-00086-5-
dc.identifier.urihttp://hdl.handle.net/10722/201164-
dc.descriptionChapter 611-
dc.description.abstractThis paper deals with light water reactor, particularly BWR type nuclear power plants, similar to Fukushima Dai-ichi Nuclear Power Plant with reactors equally vulnerable to core-melt accidents. It first re-iterates the observations and assertions made by Shinozuka (Shinozuka 2012) to recognize that the core-melt is the most critical damage event that must be mitigated by aggressive mitigation procedures if it cannot be prevented. In this regard, it is noteworthy to observe that U.S. Nuclear Energy Institute (NEI) recently intro-duced a procedure FLEX (NEI 2012) for emergency preparedness. This paper however proposes a different procedure as promoted by Shinozuka earlier (Shinozuka 2012) which is now named “Direct Core Cooling System” (DCCS). DCCS is developed making use of mobile closed-circuit water chilling system in such a way that pumps, a part of this system, are (1) directly connected by pipes to the core, (2) while minimizing their connections with any other reactor components. (1) and (2) above indicate the care that must be exer-cised not to get trapped by 3 pitfalls related to such connections. Any one of these pitfalls if trapped can com-promise effectiveness of DCCS. The mobile water chilling system is originally introduced to similar line of research by Cheung (Cheung 1991 & 2012). The cooling action by DCCS takes place as soon as intelligent sensors in the sense of engineering cybernetics detect initial sign of core-melt, and contain the core-melt lead-ing it to a cold shut down.en_US
dc.languageengen_US
dc.publisherCRC Press.-
dc.relation.ispartofSafety, Reliability, Risk and Life-Cycle Performance of Structures and Infrastructures: Proceedings of the 11th International Conference on Structural Safety and Reliability ... 2013en_US
dc.titleIntelligent damage mitigation for BWR nuclear reactorsen_US
dc.typeConference_Paperen_US
dc.identifier.emailCheung, KP: kpcheuna@hkucc.hku.hken_US
dc.identifier.authorityCheung, KP=rp00996en_US
dc.identifier.doi10.1201/b16387-660-
dc.identifier.hkuros235127en_US
dc.identifier.spage4563-
dc.identifier.epage4568-
dc.publisher.placeThe Netherlands-
dc.customcontrol.immutablesml 150120-

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