Indirect validation of fluid-to-fluid scaling criteria for modeling steam condensation based on empirical correlations and CFD simulations

Author:

Khasawneh Khalid,Jeong Yong Hoon

Funder

Korea Ministry of Science and ICT

Nuclear Safety and Security Commission

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference42 articles.

1. Steam condensation in horizontal and inclined tubes under stratifiedflow conditions;Ahn;International Journal of Heat and Mass Transfer,2019

2. Design of condensation heat exchanger for the PAFS (Passive Auxiliary Feedwater System) of the APR+ (Advanced Power Reactor Plus);Bae;Ann. Nucl. Energy,2012

3. Morozov, A., Soshkina, A., 2008. Passive core cooling systems for next generation NPPs: characteristics and state of the art, International Youth Nuclear Congress, Interlaken (Switzerland).

4. Nakamura, H., Anoda, Y., Tabata, H., Obata, H., Arai, K., Kurtia, T., 2000. Experimental investigation of thermal-hydraulic performance of PCCS with horizontal tube heat exchangers: single U-tube test. SARJ-99: Workshop on Severe Accident Research, Tokyo, Japan.

5. Scaling of two-phase flow transients using reduced pressure system and simulant fluids;Kocamustafaocullari;Nucl. Eng. Des.,1987

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