Publicado 18 números por año
ISSN Imprimir: 1064-2285
ISSN En Línea: 2162-6561
Indexed in
Upward Two-Phase Flow in a Vertical Annular Channel (Effect of Spacer Geometry)
SINOPSIS
One concern in the thermal design of a safe and economic nuclear reactor, especially in a boiling water reactor (BWR), is the heat removal from the nuclear fuel rods near the rods supporting the spacers. The spacer must be carefully designed focusing attention on the geometry of the spacer. The purpose of the present paper is to experimentally investigate the effect of the spacer geometry on the film breakdown near the spacer. A ring and a grid type spacers were used in the present experiment. Judging from the frequency of the dry patch formation and the temperature distribution near the spacer it is demonstrated that the ring type spacer is better than the grid type spacer.