CHF correlation development using local liquid velocity under ERVC conditions = 원자로용기 외벽냉각 조건에서 국부속도를 활용한 임계열유속 상관식 개발

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In-vessel retention (IVR) through external reactor vessel cooling (ERVC) is a severe accident mitigation strategy that is applied in many light water reactors (LWR). Critical heat flux (CHF) is a key parameter which indicates the success of the IVR strategy. Previous research have limitations that the CHF models were developed in terms of averaged factors such as mass flux. In this thesis, laser induced fluorescence (LIF) and particle image velocimetry (PIV) technique was coupled to measure the velocity field of the fluid in a test section. The test section simulated the gap between the reactor vessel outer wall and the insulation. Air injection was used to simulate CHF conditions in the forced circulation water loop. Curved rectangular channel with 50 cm radius was devised to simulate flow path of the reactor vessel external wall. The channel was made of transparent acrylic. CHF prediction correlation was developed based on the velocity field data acquired from the experiment.
Advisors
Jeong, Yong Hoonresearcher정용훈researcher
Description
한국과학기술원 :원자력및양자공학과,
Publisher
한국과학기술원
Issue Date
2017
Identifier
325007
Language
eng
Description

학위논문(석사) - 한국과학기술원 : 원자력및양자공학과, 2017.2,[vi, 44 p. :]

Keywords

IVR-ERVC; CHF; PIV; Liquid velocity; Local conditions; 원자로 외벽냉각; 임계열유속; 입자영상유속계; 액체속도; 국부조건

URI
http://hdl.handle.net/10203/243192
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=675321&flag=dissertation
Appears in Collection
NE-Theses_Master(석사논문)
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