Stress analysis with simplified model for a LMFBR fuel rod system = 단순화된 모델을 이용한 고속증식로 연료계의 응력 해석

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This paper is concerned with an approximate closed solution for stresses in an idealized nuclear reactor fuel system under a steady state condition. This analysis is based on the thermo-mechanical response of the fuel rod system. The pellet is modeled as elastic-plastic continuum governed by the Mohr-Coulomb yield criterion and by the flow rule. The cladding is modeled as elastic-plastic continuum governed by the Treasca criterion and by the flow rule under plane strain. Although the present model is very simplified, this can be used as a yardstick to check the accuracy of the approximate solutions obtained by the numerical technique. Numerical results, illustrating the variation of displacement and stresses under the typical Liquid Metal Fast Breeder Reactor condition, are given. A comparision between results by the present work and by the previous work shows: Interaction between the pellet and the clad occurs at high burn up, and if interaction occurs, the cladding hoop stresses due to the contact is greater than that in the creep model. This agrees with the previous discovery that, when the interaction occurs, the plasticity has a greater effect on the stresses than the creep. The lower the central void size is, the earlier the interaction takes place. This means that the existence of central void makes diminished the contact pressure.
Advisors
Lee, Byung-Ho이병호
Description
한국과학기술원 : 핵공학과,
Publisher
한국과학기술원
Issue Date
1985
Identifier
64923/325007 / 000831360
Language
eng
Description

학위논문(석사) - 한국과학기술원 : 핵공학과, 1985.2, [ vi, 68 p. ]

URI
http://hdl.handle.net/10203/49096
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=64923&flag=dissertation
Appears in Collection
NE-Theses_Master(석사논문)
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