To maintain the containment within the design limits of pressure and temperature, the advanced pressurized water reactor (APWR) designed by Westinghouse uses a passive safety system to transfer the heat from inner containment to outside. The passive containment cooling system (PCCS) includes many natural phenomena mechanisms. Steam condensation is one of the most important phenomena. Most heat is removed by steam condensation on inside surface of the containment during the postulated design basic accidents (DBA). It is very significant for engineering designing and code developing to study the mechanism of steam condensation on cold surface. There was an experiment made by University of Wisconsin on it. In this paper, the structure pressure of the pressured equipment is calculated and the tightness is also analyzed.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5581-2
PROCEEDINGS PAPER
Tightness Analysis of Pressured Equipment in Experimental Test on Steam Condensation on the Cold Surface
Lin Yang,
Lin Yang
State Nuclear Power Technology R&D Centre, Beijing, China
Search for other works by this author on:
Liyong Han
Liyong Han
State Nuclear Power Technology R&D Centre, Beijing, China
Search for other works by this author on:
Lin Yang
State Nuclear Power Technology R&D Centre, Beijing, China
Liyong Han
State Nuclear Power Technology R&D Centre, Beijing, China
Paper No:
ICONE21-15888, V004T09A062; 5 pages
Published Online:
February 7, 2014
Citation
Yang, L, & Han, L. "Tightness Analysis of Pressured Equipment in Experimental Test on Steam Condensation on the Cold Surface." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 4: Thermal Hydraulics. Chengdu, China. July 29–August 2, 2013. V004T09A062. ASME. https://doi.org/10.1115/ICONE21-15888
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