(A) numerical assessment of reflood phenomena in PWRs가압 경수형 원자로에서 재관수 현상에 대한 수치해석적 평가

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As an extension work of computer codes QUEN1D, KREWET and BEAR developed by previous workers at KAIST has been performed. This study is based on a signle flow channel, and separated two phase flow. The heat transfer selection logic is developed and the heat transfer coefficients are calculated as a function of the local flow conditions. The wall temperataure history is calculated by solving the time-dependent radial conduction equation. Comparison between predictions and PWR-FLECHT experiment data shows a relatively good agreement, but further improvement seems to be necessary for low pressure and low flloding rate conditions.
Advisors
Chun, Moon-Hyun전문헌
Description
한국과학기술원 : 핵공학과,
Publisher
한국과학기술원
Issue Date
1990
Identifier
67583/325007 / 000881507
Language
eng
Description

학위논문(석사) - 한국과학기술원 : 핵공학과, 1990.2, [ vi, 47 p. ]

Keywords

Reflood

URI
http://hdl.handle.net/10203/49250
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=67583&flag=dissertation
Appears in Collection
NE-Theses_Master(석사논문)
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