Single-Side Heated Monoblock, High Heat Flux Removal Using Water Subcooled Turbulent Flow Boiling-Reference-Cited by-同舟云学术

Single-Side Heated Monoblock, High Heat Flux Removal Using Water Subcooled Turbulent Flow Boiling

Published:2004-02-01 Issue:1 Volume:126 Page:17-21
ISSN:0022-1481
Container-title:Journal of Heat Transfer
language:en
Short-container-title:

Author:

Boyd Ronald D.¹,Cofie Penrose¹,Zhang Hongtao¹,Ekhlassi Ali¹

Affiliation:

1. Thermal Science Research Center (TSRC), College of Engineering, P.O. Box 4208, Prairie View A&M University, Prairie View, TX 77446-4208

Abstract

Plasma-facing components for fusion reactors and other high heat flux heat sinks are subjected to a peripherally nonuniform heat flux. The monoblock test section under study is a single-side heated square cross-section heat sink with a circular coolant channel bored through the center. The heated length of the test section is 180 mm. The inside diameter and outside square sides are 10 mm and 30 mm, respectively. It was subjected to a constant heat flux on one side of the outside surfaces, and the remaining portion was not heated. The exit water subcooling varied from 55 to 101°C, the exit pressure was maintained at 0.207 MPa, and the mass velocity was 0.59Mg/m2s. The results consist of three-dimensional wall temperature distributions and a display of two-dimensional quasi-boiling curves. These results are among the first full set of three-dimensional wall temperature measurements for a single-side heated monoblock flow channel which contains the effects of conjugate heat transfer for turbulent, subcooled flow boiling. In the single-phase region, good predictability resulted when the thermal hydraulic diameter was used.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Condensed Matter Physics,General Materials Science

Link

http://asmedigitalcollection.asme.org/heattransfer/article-pdf/126/1/17/5736809/17_1.pdf

Reference22 articles.

1. Boyd, R.D. , 1999, “Single-Side Conduction Modeling for High Heat Flux Coolant Channels,” Fusion Technol., 35, pp. 8–16.

2. Marshall, T.D., Youchison, D.L., and Cadwallader, L.C., 2001, “Modeling the Nukiyama Curve for Water-Cooled Fusion Divertor Channels,” Fusion Technol., 35, pp. 8–16.

3. Boscary, J., Araki, M., and Akiba, M., 1997, “Critical Heat Flux Database of JAERI for High Heat Flux Components for Fusion Applications,” JAERI-Data/Code 97-037, Japan Atomic Energy Research Institute.

4. Liu, W., Nariari, H., and Inasaka, F., 2000, “Prediction of Critical Heat Flux for Subcooled Flow Boiling,” Int. J. Heat Mass Transfer, 43, pp. 3371–3390.

5. Youchison, D.L., Schlosser, J., Escourbiac, F., Ezato, K., Akiba, M., and Baxi, C.B., 1999, “Round Robin CHF Testing of an ITER Vertical Target Swirl Tube,” 18th IEEE/NPSS Symposium on Fusion Engineering, Albuquerque, NM, pp. 385–387.