Subcooled flow boiling from the bottom of a large-diameter tube
Book
·
OSTI ID:445442
- Purdue Univ., West Lafayette, IN (United States). School of Nuclear Engineering
- Ontario Hydro Technologies, Toronto, Ontario (Canada)
The temperature distribution in CANDU nuclear reactor fuel channels, after contact between the pressure tube and the calandria tube, is an important factor in evaluating pressure tube structural integrity. This report describes laboratory tests that were carried out to study the heat transfer on the outer surface of the calandria under boiling conditions that are similar to those expected in the reactor if the pressure tube comes in contact with the calandria tube during normal operation. The measured heat transfer is compared to predictions based on the correlation currently being used. It was observed that the moderator bulk temperature did not have a significant effect on the results once boiling was fully developed. The results are consistent with predictions from correlations in the open literature commonly used for pool boiling from small diameter cylinders with the entire surface heated. Although the current tests were performed using light water at approximately 112 kPa, only minor changes are expected for heavy water and higher pressures expected in the calandria.
- OSTI ID:
- 445442
- Report Number(s):
- CONF-950828--; ISBN 0-7918-1713-X
- Country of Publication:
- United States
- Language:
- English
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