A series of experiments was performed for rewetting phenomena on dryed-out fuel rod surfaces under post-BT (Boiling Transition) conditions with high-pressure and high-water flow rate simulating anticipated operational occurrences of a BWR. An analytical model for rewetting velocity, defined by a propagation velocity of a quench front, has been developed on the basis of the experimental results. The rewetting for the post-BT condition is characterized by the faster propagation of the quench front than that for reflood phase conditions during a postulated large-break loss-of-coolant accident. In order to provide an explanation of this characteristic, the present analytical model took an effect of a precursory cooling into account by modifying the existing correlation by Sun-Dix-Tien [1] which is based on a one-dimensional analysis in a flow direction during the reflood phase. The present model demonstrates that the precursory cooling can significantly increase the rewetting velocity by more than an order of magnitude. Applying the experimental correlation developed in the separately conducted experiment into the heat transfer coefficient in the present model at a wet and a dry region with precursory cooling, our data of the rewetting velocity as well as the wall temperature profiles for the variable flow rates are successfully predicted.
Skip Nav Destination
17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4353-6
PROCEEDINGS PAPER
Measurement and Analysis for Rewetting Velocity Under Post-BT Conditions During Anticipated Operational Occurrence of BWR Available to Purchase
Yasuteru Sibamoto,
Yasuteru Sibamoto
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Search for other works by this author on:
Yu Maruyama,
Yu Maruyama
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Search for other works by this author on:
Hideo Nakamura
Hideo Nakamura
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Search for other works by this author on:
Yasuteru Sibamoto
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Yu Maruyama
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Hideo Nakamura
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Paper No:
ICONE17-75287, pp. 287-296; 10 pages
Published Online:
February 25, 2010
Citation
Sibamoto, Y, Maruyama, Y, & Nakamura, H. "Measurement and Analysis for Rewetting Velocity Under Post-BT Conditions During Anticipated Operational Occurrence of BWR." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance. Brussels, Belgium. July 12–16, 2009. pp. 287-296. ASME. https://doi.org/10.1115/ICONE17-75287
Download citation file:
6
Views
Related Proceedings Papers
Related Articles
Calculations of Combined Radiation and Convection Heat Transfer in Rod Bundles Under Emergency Cooling Conditions
J. Heat Transfer (August,1976)
Measurement and Analysis for Rewetting Velocity Under Post-BT Conditions During Anticipated Operational Occurrence of BWR
J. Eng. Gas Turbines Power (October,2010)
Sub-Channel Analysis of a Hexagonal Sub-Assembly: Influence of Blockage and Axial Power Distribution on Critical Heat Flux
J. Thermal Sci. Eng. Appl (December,2021)
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)
LOCA Frequencies Estimated from Operating Experience (PSAM-0282)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Analysis of Accident Progression and Source Terms in Seismic Events for BWR-4 Plant (PSAM-0053)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)