This paper presents the results of experimental investigations into two-phase mass transport in a coarse packed bed representing the Canada Deuterium Uranium (CANDU) end shield. This work contributes to understanding of phenomena impacting in-vessel retention (IVR) during postulated severe accidents in CANDU reactors. The air barbotage technique was used to represent boiling at the calandria tubesheet surface facing the inner cavity of the end shield. Qualitative observations of the near-wall two-phase region were made during air injection. In addition, flow visualization was carried out through the addition of dye to the water. Air flow rate, shielding ball diameter, and cavity dimensions were varied within relevant ranges; and the impact of these parameters on the near-wall region was identified. A brief review of the relevant knowledge base is presented, allowing demonstration of the applicability of the test parameters. The observed phenomena are compared to published results involving similar geometries with capillary porous media.
Skip Nav Destination
Article navigation
April 2017
Research-Article
Results of Air Barbotage Experiments Simulating Two-Phase Flow in a CANDU End Shield During In-Vessel Retention
Justin H. Spencer
Justin H. Spencer
Canadian Nuclear Laboratories,
Chalk River, ON K0J 1J0, Canada
Chalk River, ON K0J 1J0, Canada
Search for other works by this author on:
Justin H. Spencer
Canadian Nuclear Laboratories,
Chalk River, ON K0J 1J0, Canada
Chalk River, ON K0J 1J0, Canada
Manuscript received July 20, 2016; final manuscript received November 30, 2016; published online March 1, 2017. Assoc. Editor: Srikumar Banerjee.
ASME J of Nuclear Rad Sci. Apr 2017, 3(2): 021008 (10 pages)
Published Online: March 1, 2017
Article history
Received:
July 20, 2016
Revised:
November 30, 2016
Citation
Spencer, J. H. (March 1, 2017). "Results of Air Barbotage Experiments Simulating Two-Phase Flow in a CANDU End Shield During In-Vessel Retention." ASME. ASME J of Nuclear Rad Sci. April 2017; 3(2): 021008. https://doi.org/10.1115/1.4035566
Download citation file:
Get Email Alerts
Cited By
Radiation Monitoring for Volatilized Zinc Contamination Using Gamma-Ray Imaging and Spectroscopy
ASME J of Nuclear Rad Sci
Related Articles
Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor
ASME J of Nuclear Rad Sci (October,2016)
Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications
ASME J of Nuclear Rad Sci (April,2017)
Special Section: Pressurized Heavy Water Reactors Safety
ASME J of Nuclear Rad Sci (April,2017)
Fukushima Unit 2 Accident Simulation With MELCOR 2.1
ASME J of Nuclear Rad Sci (April,2018)
Related Proceedings Papers
Related Chapters
Insights and Results of the Shutdown PSA for a German SWR 69 Type Reactor (PSAM-0028)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Critical Heat Flux in Flow Boiling
Two-Phase Heat Transfer
Post-CHF Heat Transfer in Flow Boiling
Two-Phase Heat Transfer