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Experimental investigation of two-phase natural circulation loop as passive containment cooling system

Authors
Lim, S.T.Kim, K.M.Kim, H.Jerng, D.-W.Ahn, H.S.
Issue Date
Dec-2021
Publisher
Korean Nuclear Society
Keywords
Direct quality measurement; Liquid vapor separator; Passive containment cooling system; Two phase natural convection
Citation
Nuclear Engineering and Technology, v.53, no.12, pp 3918 - 3929
Pages
12
Journal Title
Nuclear Engineering and Technology
Volume
53
Number
12
Start Page
3918
End Page
3929
URI
https://scholarworks.bwise.kr/cau/handle/2019.sw.cau/51459
DOI
10.1016/j.net.2021.07.004
ISSN
1738-5733
Abstract
In this study, we experimentally investigate of a two-phase natural circulation loop that functions as a passive containment cooling system (PCCS). The experimental apparatus comprises two loops: a hot loop, for simulating containment under severe accidents, and a natural circulation loop, for simulating the PCCS. The experiment is conducted by controlling the pressure and inlet temperature of the hot loop in the range of 0.59–0.69 MPa (abs) and 119.6–158.8 °C, respectively. The heat balance of the hot loop is established and compared with a natural circulation loop to assess the thermal reliability of the experimental apparatus, and an additional system is installed to measure the vapor mass flow rate. Furthermore, the thermal–hydraulic characteristics are considered in terms of a temperature, mass flow rate, heat transfer coefficient (HTC), etc. The flow rate of the natural circulation loop is induced primarily by flashing, and a distortion is observed in the local HTC because of the fully develop as well as subcooled boiling. As a result, we present the amount of heat capacity that the PCCS can passively remove according to the experimental conditions and compared the heat transfer performance using Chen's and Dittus-Boelter correlation. © 2021 Korean Nuclear Society
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Jerng, Dong Wook
공과대학 (에너지시스템 공학부)
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