Çolak, ÜnerBölme, Anıl B.Köse, Serhat2018-06-252018-06-252000-10Çolak, Ü., Bölme, A. B. ve Köse, S., (2000). Analysis of WWER-440 fuel performace with FRAPCON-3. I. Eurasia Conference on Nuclear Science and Its Application, Presentations, Vol 1, (s. 42-47). 23-27 October 2000. İzmir, Turkey.http://kurumsalarsiv.tenmak.gov.tr/handle/20.500.12878/672I. Avrasya Nükleer Bilimler ve Uygulamaları Konferansı : 23-27 Ekim 2000. İzmir, Türkiye.Nuclear reactor fuel rods are essential nuclear components from the operational and safety points of view. Recent experience in nuclear industry is to increase fuel discharge bumup as much as possible. This, in turn, raise the question of fuel rod integrity and radioactivity release at extended bumup and especially during operational transients. At this point, cladding may be considered as the most vital and vulnerable component of the fuel road. Cladding behavior normally is deterioted as bumup increases and power history dependency is significant. In this study, steady-state and long term transient behavior of WWER-440 fuel elements is analyzed with FRAPCON-3 computer code. Operational parameters which are related with the overall reactor safety evaluated as a function of fuel bumup. Especially, the effect of power ramp on mechanical parameters and fission gas release analyzed and an assessment is made. Comparison is made for the parameters in cases of relatively fresh fuel and at extended bumup. Hence, the variation of fuel behavior for high bumup fuel is presented.enginfo:eu-repo/semantics/openAccessAnalysis of fuel performaceYakıt performans analiziWWER-440FRAPCON-3conferenceObject4247