Passive decay heat removal (PDHR) system is important to the safety of integral pressurized water reactor (IPWR). In small break LOCA sequence, the depressurization of the reactor pressure vessel (RPV) is achieved by the PDHR that remove the decay heat by condensing steam directly through the SGs inside the RPV at high pressure. The non-condensable gases in the RPV significantly weaken the heat transfer capability of PDHR. This paper focus on the non-condensable gas effects in passive decay heat removal system at high pressure. A series of experiments are conducted in the Institute of Nuclear and New Energy Technology test facility with various heating power and non-condensable gas volume ratio. The results are significant to the optimizing design of the PDHR and the safety operation of the IPWR.
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2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5003-9
PROCEEDINGS PAPER
Experimental Research on Non-Condensable Gases Effects in Passive Decay Heat Removal System
Haijun Jia,
Haijun Jia
Tsinghua University, Beijing, China
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Li Weihua
Li Weihua
Tsinghua University, Beijing, China
Search for other works by this author on:
Yang Liu
Tsinghua University, Beijing, China
Haijun Jia
Tsinghua University, Beijing, China
Li Weihua
Tsinghua University, Beijing, China
Paper No:
ICONE24-60769, V003T09A060; 7 pages
Published Online:
October 25, 2016
Citation
Liu, Y, Jia, H, & Weihua, L. "Experimental Research on Non-Condensable Gases Effects in Passive Decay Heat Removal System." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 3: Thermal-Hydraulics. Charlotte, North Carolina, USA. June 26–30, 2016. V003T09A060. ASME. https://doi.org/10.1115/ICONE24-60769
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