Main Steam Line Break (MSLB) accident will lead to the release of high-energy steam inside the containment, then cause the pressure and temperature of containment rise, which threatening containment integrity and the normal operation of the containment equipment. Containment equipment layout will affect the flow of steam, while the break position, steam temperature and other factors also affect the temperature distribution inside the containment. Test bench was reconstructed on the original foundation, but analogs of Pressure Vessel and CMT have not been arranged in the simulated reactor containment at this stage. Experiments with steam as the working fluid were carried out at ambient pressure environment. Steam injected into the containment and after reaching steady state data acquisition card got temperature values of each measuring point. The main purpose of this work is to study the temperature distribution inside containment and heat transfer phenomenon of steel shell in MSLB accident. Experimental results show that the temperature stratification appears in the containment, although the temperature distribution in the shell is different under different operating conditions.
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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:
978-0-7918-5004-6
PROCEEDINGS PAPER
An Experimental Study of Small Sized Reactors Containment Heat Transfer Phenomena Under MSLB Accident
YeYun Wang,
YeYun Wang
North China Electric Power University, Beijing, China
Search for other works by this author on:
ShengFei Wang
ShengFei Wang
North China Electric Power University, Beijing, China
Search for other works by this author on:
YeYun Wang
North China Electric Power University, Beijing, China
ShengFei Wang
North China Electric Power University, Beijing, China
Paper No:
ICONE24-60276, V004T14A012; 6 pages
Published Online:
October 25, 2016
Citation
Wang, Y, & Wang, S. "An Experimental Study of Small Sized Reactors Containment Heat Transfer Phenomena Under MSLB Accident." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management. Charlotte, North Carolina, USA. June 26–30, 2016. V004T14A012. ASME. https://doi.org/10.1115/ICONE24-60276
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