The cooling of the Ex-vessel in Light-Water-Reactors has been proposed to maintain reactor vessel integrity during severe accident. The critical heat flux — CHF — from the underside of down-facing convex surfaces, like hemispheres, is important to the assessment of the cooling. The authors examined CHFs on inclined plates under saturated boiling experimentally, focusing on the effect of the inclination angle on the CHF and characteristic length and velocity of coalesced bubbles near the heater at the CHF. In this study, the critical heat fluxes on the inclined plates in saturated boiling were investigated analytically by using the macrolayer model and the Kelvin-Helmholtz instability, based on our previous experimental report. Furthermore, the present model was developed for the CHF on a hemispheric surface. In the present model, the most dangerous wavelength and propagative velocity of the wave in the Kelvin-Helmholtz instability for ideal fluid with vapor flow of finite thickness and surface tension on liquid-vapor interface were calculated to determine the length and the velocity of the coalesced bubble on the heating surface at CHF. The time covered over the heater with the bubble was estimated as the calculated value with the length divided by the velocity. The predictions of the present CHF model by using the macrolayer model for CHF and the Kelvin-Helmholtz instability for the characteristic values of the coalesced bubble agree well with previous experimental data for CHF on inclined plates with 30 to 180 degree in orientation. Furthermore, the present model given as a function of the inclination angle relative to the horizontal downward plate was extended to CHF on a hemispheric surface. The CHFs obtained by the present model are in qualitative agreement with experimental data on hemispheres reported by some investigators.
Skip Nav Destination
10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3597-9
PROCEEDINGS PAPER
Study on Ex-Vessel Cooling of RPV: Model Analysis of Critical Heat Flux on Inclined Plate Facing Downward and Development to Hemispherical Surface
Hiroyasu Ohtake,
Hiroyasu Ohtake
Kogakuin University, Tokyo, Japan
Search for other works by this author on:
Yasuo Koizumi
Yasuo Koizumi
Kogakuin University, Tokyo, Japan
Search for other works by this author on:
Hiroyasu Ohtake
Kogakuin University, Tokyo, Japan
Yasuo Koizumi
Kogakuin University, Tokyo, Japan
Paper No:
ICONE10-22316, pp. 481-486; 6 pages
Published Online:
March 4, 2009
Citation
Ohtake, H, & Koizumi, Y. "Study on Ex-Vessel Cooling of RPV: Model Analysis of Critical Heat Flux on Inclined Plate Facing Downward and Development to Hemispherical Surface." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 14–18, 2002. pp. 481-486. ASME. https://doi.org/10.1115/ICONE10-22316
Download citation file:
13
Views
Related Proceedings Papers
Related Articles
Observations of the Critical Heat Flux Process During Pool Boiling of FC-72
J. Heat Transfer (April,2014)
Microporous Coatings to Maximize Pool Boiling Heat Transfer of Saturated R-123 and Water
J. Heat Transfer (August,2015)
Effects of Pressure and a Microporous Coating on HFC-245fa Pool Boiling Heat Transfer
J. Heat Transfer (October,2014)
Related Chapters
Post-CHF Heat Transfer in Flow Boiling
Two-Phase Heat Transfer
Critical Heat Flux in Flow Boiling
Two-Phase Heat Transfer
Liquid Cooled Systems
Thermal Management of Telecommunication Equipment, Second Edition