Development of the best-estimate computer code for reflood transient analysis = 가압 경수형 원자로에서의 재관수 현상의 정밀 해석을 위한 computer code 의 개발

As an extension work of computer codes QUENID and KREWET developed by previous workers at KAIST, an improved code entitiled BEAR has been developed. The BEAR code is based on mechanistic models developed to analyze bottom reflooding of a single flow channel and its associated fuel rod. From the hydrodynamic point of view the flow channel is divided into a singlephase liquid region, a continuous liquid two-phase region, and a dispersed liquid region. The heat transfer coefficients are the functions of the local flow conditions. The wall temperature history is calculated by solving the time-dependent radial conduction equation. Quench pront propagation is treated separately from the overall heat transfer calculations by models including the effects of axial conduction. Comparison of the predictions of the BEAR code with the PWR-FLECHT experiment data show a relatively good agreement, but further improvement seems to be necessary for low pressure and low flooding rate conditions.
Advisors
Chun, Moon-Hyunresearcher전문헌researcher
Publisher
한국과학기술원
Issue Date
1986
Identifier
65449/325007 / 000841108
Language
eng
Description

학위논문(석사) - 한국과학기술원 : 핵공학과, 1986.2, [ [vi], 69 p. ]

URI
http://hdl.handle.net/10203/49115
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=65449&flag=t
Appears in Collection
NE-Theses_Master(석사논문)
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