Experimental study on boiling transition under flow-power oscillating condition for hyper ABWR
- 1. Toshiba Corporation Power Systems Company, Yokohama, Kanagawa (Japan)
Description
In the envisioned high-power density core plant, the degradation of stability is concerned that is attributed to the shortening of rod heat conduction time constant upon the dense fuel grid and the increment of pressure drop caused by the wall friction. Under power and flow oscillating conditions, the two-phase flow behavior might be different from that under the steady conditions. Therefore, the thermal-hydraulic test using the rod bundle under oscillating conditions were performed to obtain the verification data for the analysis code. In this paper, the test results were described. It was found that the critical power decreased under flow oscillating conditions compared with under steady conditions, and the power oscillation had a little effect on the critical power. (author)
Additional details
Publishing Information
- Journal Title
- Nippon Kikai Gakkai Ronbunshu, B Hen
- Journal Volume
- 75
- Journal Issue
- 751
- Journal Page Range
- p. 397-399
- ISSN
- 0387-5016
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 40084238
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; CRITICAL HEAT FLUX; FEASIBILITY STUDIES; FLUID FLOW; HEAT TRANSFER; MULTIPHASE FLOW; NUCLEAR FUELS; OSCILLATIONS; POWER; POWER DENSITY; STABILITY; THERMAL HYDRAULICS; TRANSITION BOILING
- Descriptors DEC
- BOILING; ENERGY SOURCES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID MECHANICS; FUELS; HEAT FLUX; HYDRAULICS; MATERIALS; MECHANICS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs., 7 figs.