AN INVESTIGATION FOR USAGE OF GRAPHITE POWDER-HELIUM SUSPENSION AS RACTOR COOLANT IN A HTGR

ALTAÇ Z., YUCEL N.

NUCLEAR ENGINEERING AND DESIGN, vol.131, no.1, pp.71-80, 1991 (SCI-Expanded) identifier identifier identifier

  • Publication Type: Article / Article
  • Volume: 131 Issue: 1
  • Publication Date: 1991
  • Doi Number: 10.1016/0029-5493(91)90318-c
  • Journal Name: NUCLEAR ENGINEERING AND DESIGN
  • Journal Indexes: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Page Numbers: pp.71-80
  • Anadolu University Affiliated: No

Abstract

This study's aim is to perform a numerical experiment to examine the enhancement of heat transfer in high-temperature gas-cooled reactors (HTGR) by using gas-particulate (graphite powder-helium) suspension as reactor coolant. At very high temperatures, the radiative heat can be profoundly improved compared to gas alone because of the large absorptivity of the cloud of fine particles. For every high-temperature flow situation where radiation is a significant mode of heat transfer, there exists an optimum loading ratio (mass of graphite to that of He) and particle size for which maximum heat-transfer rates are achieved. The study uses typical HTGR data to examine the heat-transfer phenomena and determine the mass of graphite, optimum particle size, and the influence of other parameters which will result in maximum heat transfer.