(An) evaluation method of the number of failed fuel rods based on the dependency of the fission product release on the defect size = 결함의 크기에 의존하는 핵분열 생성물 누출에 기초한 파손 핵연료 수의 평가 방법

A model for estimating the number of failed fuel rod and defect size based on the primary coolant activity is presented. Transport phenomena in the gap is represented by a diffusion process to attain a link with the defect size. The gap attenuation factor dependent on the defect size and the radioactive decay constant is introduced. It is shown that if the effective defect size is larger than the thickness of the clad, the gap attenuation factor is weekly dependent on the defect size. From the values of the gap attenuation factors, the rod escape rate coefficients can be evaluated. On the basis of the present model, the ENOFS computer program has been developed and applied to cycles 1 and 2 of KORI-1. The number of fuel failures deduced from ENOFS calculations was between four and five with small defect size for cycle 1. On the other hand, about 15 failed fuel rods with small defect size and one with more large defect size were predicted for cycle 2. The end of cycle 1 sipping test results showed that there were two assemblies with failed fuel rods, and for cycle 2 there were two fuel assemblies which included a few large defective fuels.
Advisors
Chun, Moon-Hyunresearcher전문헌researcher
Publisher
한국과학기술원
Issue Date
1992
Identifier
60256/325007 / 000901084
Language
eng
Description

학위논문(석사) - 한국과학기술원 : 원자력공학과, 1992.2, [ viii, 50 p. ]

URI
http://hdl.handle.net/10203/49053
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=60256&flag=t
Appears in Collection
NE-Theses_Master(석사논문)
Files in This Item
There are no files associated with this item.
  • Hit : 94
  • Download : 0
  • Cited 0 times in thomson ci

qr_code

  • mendeley

    citeulike


rss_1.0 rss_2.0 atom_1.0