The present work focuses on the study of two-phase flow behavior called “Intermittent
Buoyancy Induced Flow” (IBIF) resulting from the loss of coolant circulation in a
CANDU nuclear reactor core. The main objectives are to study steam bubble formation
and migration through the pressure tube and into the feeder tubes and headers, and to
study the effect of pressure tube sagging on the two-phase flow behavior during IBIF.
Experiments are conducted using air and water flow at atmospheric pressure to
qualitatively examine the IBIF phenomena. The test showed oscillating periodic behavior
in the void fraction as the air vents.
In addition to this, a mathematical model based on a simplified momentum balance for the
liquid and gas phases was formulated. The model was further solved and compared to the
experimental data. The model predictions showed a reasonable agreement within the
investigated range of void fractions.
| Identifer | oai:union.ndltd.org:LACETR/oai:collectionscanada.gc.ca:OTU.1807/18784 |
| Date | 12 February 2010 |
| Creators | Karchev, Zheko |
| Contributors | Kawaji, Masahiro |
| Source Sets | Library and Archives Canada ETDs Repository / Centre d'archives des thèses électroniques de Bibliothèque et Archives Canada |
| Language | en_ca |
| Detected Language | English |
| Type | Thesis |
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