Discrepancy has long existed about nozzle diameter effect on critical flow rate in two-phase critical flow analysis. The issue is of great importance because it involves whether the scaling test can accurately simulate the actual process during loss of coolant accident. A series of transient critical flow experiments has been performed in China Institute of Atomic Energy (CIAE), which aims to study the nozzle diameter effect. The diameter of adopted test nozzle is 5mm, 10mm and 15mm, respectively. The experiment result shows that the discharge mass flow rate decreases as nozzle diameter increases. This is contradictory with the results obtained from steady state critical flow experiment. Comprehensive analysis shows that the diameter effect observed in transient critical flow experiment is transient effect caused by system pressure change, and the mechanism is the dynamic unbalance in the transient period. It is presumed that for the same test section with a certain diameter, if the pressure change velocity is different, the measured critical flow rate will be different. The conclusion is validated in the pressurization and depressurization blowdown test. It| is arrived that nozzle diameter has no direct effect on critical flow rate, and thus the discrepancy on diameter effect is clarified.
Skip Nav Destination
2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5784-7
PROCEEDINGS PAPER
Investigation of Diameter Effect on Critical Flow
Zhao Minfu,
Zhao Minfu
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Lv Yufeng,
Lv Yufeng
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Zhang Dongxu,
Zhang Dongxu
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Chen Yuzhou,
Chen Yuzhou
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Bi Keming
Bi Keming
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Zhao Minfu
China Institute of Atomic Energy, Beijing, China
Lv Yufeng
China Institute of Atomic Energy, Beijing, China
Zhang Dongxu
China Institute of Atomic Energy, Beijing, China
Chen Yuzhou
China Institute of Atomic Energy, Beijing, China
Bi Keming
China Institute of Atomic Energy, Beijing, China
Paper No:
ICONE25-67076, V006T08A075; 4 pages
Published Online:
October 17, 2017
Citation
Minfu, Z, Yufeng, L, Dongxu, Z, Yuzhou, C, & Keming, B. "Investigation of Diameter Effect on Critical Flow." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 6: Thermal-Hydraulics. Shanghai, China. July 2–6, 2017. V006T08A075. ASME. https://doi.org/10.1115/ICONE25-67076
Download citation file:
15
Views
Related Proceedings Papers
Related Articles
Effects of Trenched Holes on Film Cooling of a Contoured Endwall Nozzle Vane
J. Turbomach (July,2012)
An Investigation of the Collapse and Surface Rewet in Film Boiling in Forced Vertical Flow
J. Heat Transfer (May,1975)
Brittle Failure Assessment of a PWR-RPV for Operating Conditions and Loss of Coolant Accident
J. Pressure Vessel Technol (August,2008)
Related Chapters
Development of Nuclear Boiler and Pressure Vessels in Taiwan
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition
Introduction
Nuclear Reactor Thermal-Hydraulics: Past, Present and Future
Czech and Slovakian Codes
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition