Development of an improved methodology for estimating the number of failed fuel rods in PWRs가압경수로에서의 손상핵연료 수를 평가하기 위한 개선된 방법의 개발

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dc.contributor.advisorChun, Moon-Hyun-
dc.contributor.advisor전문헌-
dc.contributor.authorLee, Sang-Kyu-
dc.contributor.author이상규-
dc.date.accessioned2011-12-14T08:15:09Z-
dc.date.available2011-12-14T08:15:09Z-
dc.date.issued1997-
dc.identifier.urihttp://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=114543&flag=dissertation-
dc.identifier.urihttp://hdl.handle.net/10203/49370-
dc.description학위논문(석사) - 한국과학기술원 : 원자력공학과, 1997.2, [ x, 54 p. ]-
dc.description.abstractAn improved methodology for estimating the number of failed fuel rods based on the primary coolant activity in operating PWRs has been developed. This method deals with both the diffusion and the kinetic models. In case of small, medium, and large cladding failures, the diffusion model which can consider different sizes of failure is used, whereas for gross cladding failures the kinetic model is used. In the kinetic model, the release-to-birth rate ratio (R/B) is represented as a linear function of the number of failed fuel rods. This has been done by expressing the gap escape rate coefficient in terms of the slope of log(R/B) versus log λ. Incorporating these models, the CAAP (Coolant Activity Analysis Program) computer program, running under a graphical user interface, has been developed to estimate the number of failed fuel rods based on the primary coolant activity and has been applied to the cases of 26 cycles, including 21 cycles of foreign PWRs and 5 cycles of domestic PWRs, for which ultrasonic testings were performed at end of cycle (EOC). The results show that the present method gives better predictions than the existing computer codes such as IODYNE and CADE.eng
dc.languageeng-
dc.publisher한국과학기술원-
dc.subjectFailed nuclear fuel rod-
dc.subjectCAAP-
dc.subject핵분열생성물 방출-
dc.subject손상핵연료-
dc.subjectFisson product release-
dc.titleDevelopment of an improved methodology for estimating the number of failed fuel rods in PWRs-
dc.title.alternative가압경수로에서의 손상핵연료 수를 평가하기 위한 개선된 방법의 개발-
dc.typeThesis(Master)-
dc.identifier.CNRN114543/325007-
dc.description.department한국과학기술원 : 원자력공학과, -
dc.identifier.uid000953419-
dc.contributor.localauthorLee, Sang-Kyu-
dc.contributor.localauthor이상규-
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