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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