Channel blockage accident analysis for research reactors with MTR-TYPE fuel elements

dc.contributor.authorYılmazer, Ayhan
dc.contributor.authorYavuz, Hasbi
dc.contributor.departmentTAEK-NGDtr_TR
dc.date.accessioned2018-06-25T12:58:33Z
dc.date.available2018-06-25T12:58:33Z
dc.date.issued2000-10
dc.descriptionI. Avrasya Nükleer Bilimler ve Uygulamaları Konferansı : 23-27 Ekim 2000. İzmir, Türkiye.tr_TR
dc.description.abstractIt is the purpose of this study to investigate the feasibility of removing the residual decay heat from core of TR-2 ,which is a pool-type research reactor, after a channel blockage accident event and to identify the principal factors involved in cooling process. To analyze this accident scenery, THEAP-I(1) computer code, which is a single phase transient 3-D structure/1-D flow thermal hydraulics code developed with the aim to contribute mainly to the safety analysis of the open pool research reactors, was modified and used. All of the analysis results figured out the fact that the core melting was inevitable in case of an uninterrupted operation (continuous operation) preceding a channel blockage accident of the TR-2 Reactor. Such a result will even be met if the blockage occurs only in a single fuel element. The results of analysis are expressed in terms of temperature field distribution as a function of time.tr_TR
dc.identifier.citationYılmazer, A. ve Yavuz, H., (2000). Channel blockage accident analysis for research reactors with MTR-TYPE fuel elements. I. Eurasia Conference on Nuclear Science and Its Application, Presentations, Vol 1, (s. 65-76). 23-27 October 2000. İzmir, Turkey.tr_TR
dc.identifier.endpage76tr_TR
dc.identifier.startpage65tr_TR
dc.identifier.urihttp://kurumsalarsiv.tenmak.gov.tr/handle/20.500.12878/675
dc.language.isoengtr_TR
dc.publisherTurkish Atomic Energy Authoritytr_TR
dc.rightsinfo:eu-repo/semantics/openAccesstr_TR
dc.subjectNuclear reactors
dc.subjectNükleer reaktörler
dc.subjectAccident analysistr_TR
dc.subjectKaza analizitr_TR
dc.subjectResearch reactorstr_TR
dc.subjectAraştırma reaktörleritr_TR
dc.subjectMTR-TYPE fuel elementstr_TR
dc.subjectMTR-TİP yakıt elementleritr_TR
dc.subjectTR-2 reactortr_TR
dc.subjectTR-2 reaktörütr_TR
dc.titleChannel blockage accident analysis for research reactors with MTR-TYPE fuel elementstr_TR
dc.typeconferenceObjecttr_TR
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