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dc.contributor.authorBüke, Tayfun
dc.contributor.authorAYTAN, ÖZGÜR
dc.date.accessioned2021-03-04T09:19:49Z
dc.date.available2021-03-04T09:19:49Z
dc.date.issued2011
dc.identifier.citationAYTAN Ö., Büke T., "Sipping tests for the irradiated fuel elements of the TR-2 research reactor", KERNTECHNIK, cilt.76, sa.2, ss.121-125, 2011
dc.identifier.issn0932-3902
dc.identifier.otherav_67b5cedd-5c33-46e9-b6c8-b19916df7372
dc.identifier.othervv_1032021
dc.identifier.urihttp://hdl.handle.net/20.500.12627/71971
dc.identifier.urihttp://www.nuclear-engineering-journal.com/KT110120
dc.identifier.urihttps://doi.org/10.3139/124.110120
dc.description.abstractSipping tests have been performed for fuel elements of the TR-2 reactor at Cekmece Nuclear Research and Training Center (CNRTC), in order to find out which one failed in the core. A sipping assembly has been constructed and placed in the pool of the TR-2 reactor. The assembly identifies leaking fuel elements by collecting and measuring (137)Cs that leak out from the defective fuel elements. 31 fuel elements in the reactor have been tested for the clad integrity. The measured (137)Cs activity of the fuel element with an identification number S-104 is a 10247 Bq/(0.31). This value is approximately 234 times greater than the average of the other tested fuel elements in the reactor.
dc.language.isoeng
dc.subjectFizik
dc.subjectTemel Bilimler (SCI)
dc.subjectNükleer Fizik
dc.subjectTemel Bilimler
dc.subjectNÜKLEAR BİLİMİ VE TEKNOLOJİSİ
dc.titleSipping tests for the irradiated fuel elements of the TR-2 research reactor
dc.typeMakale
dc.relation.journalKERNTECHNIK
dc.contributor.departmentMuğla Sıtkı Koçman Üniversitesi , ,
dc.identifier.volume76
dc.identifier.issue2
dc.identifier.startpage121
dc.identifier.endpage125
dc.contributor.firstauthorID610480


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