Thermal hydraulic & neutronic analysis of dry cask storage systems for spent nuclear fuels

dc.contributor.authorYavuz, Ufuk
dc.contributor.authorZabunoğlu, H. Okan
dc.contributor.departmentTAEK-NGDtr_TR
dc.date.accessioned2018-07-11T13:04:41Z
dc.date.available2018-07-11T13:04:41Z
dc.date.issued2000-10
dc.descriptionI. Avrasya Nükleer Bilimler ve Uygulamaları Konferansı : 23-27 Ekim 2000. İzmir, Türkiye.tr_TR
dc.description.abstractInterim spent fuel storage systems must provide for the safe receipt, handling, retrieval and storage of spent nuclear fuel before reprocessing or disposal. In the context of achieving these objectives, the following features of the design were taken into consideration for metal shielded type storage systems; to maintain fuel subcritical, to remove spent fuel residual heat, to provide for radiation protection. These features in the design of a dry cask storage system were analyzed by employing COBRASFS and SCALE4.4 (ORIGEN, XSDOSE, CSAS6 ) codes for normal operation of the system under study. In accordance with safety assurance limits of International Atomic Energy Authority (IAEA), appropriate designs for Dry Cask Storage Systems (DCSS) were reached for 33000, 45000, and 55000 MWd/t bumup values and 5 and 10 years of cooling periods for spent fuel to be stored (Table 1).tr_TR
dc.identifier.citationYavuz, U., Zabunoğlu, H. O., (2000). Thermal hydraulic & neutronıc analysis of dry cask storage systems for spent nuclear fuels. I. Eurasia Conference on Nuclear Science and Its Application, Presentations, Vol 1, (s. 328-332). 23-27 October 2000. İzmir, Turkey.tr_TR
dc.identifier.endpage332tr_TR
dc.identifier.startpage328tr_TR
dc.identifier.urihttp://kurumsalarsiv.tenmak.gov.tr/handle/20.500.12878/710
dc.language.isoengtr_TR
dc.publisherTurkish Atomic Energy Authoritytr_TR
dc.relation.journalI. Eurasia Conference on Nuclear Science and Its Application : Presentations, 23-27 October 2000. İzmir, Turkey.tr_TR
dc.rightsinfo:eu-repo/semantics/openAccesstr_TR
dc.subjectSpent nuclear fuelstr_TR
dc.subjectTükenmiş nükleer yakıtlartr_TR
dc.subjectDry cask storage systemstr_TR
dc.subjectKuru hazne depolama sistemleritr_TR
dc.subjectThermal hydraulic & neutronic analysistr_TR
dc.subjectTermal hidrolik ve nötronik analiztr_TR
dc.titleThermal hydraulic & neutronic analysis of dry cask storage systems for spent nuclear fuelstr_TR
dc.typeconferenceObjecttr_TR
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