1. A Study of the Flow Characteristics in the Core Region of the Sandia Engineering Reactor
- Author
-
Thomas T. Castonguay, Philip E. Bocquet, Richard K. Traeger, Moeller, James A., Thomas T. Castonguay, Philip E. Bocquet, Richard K. Traeger, and Moeller, James A.
- Subjects
- Chemical Engineering
- Abstract
The core region of a nuclear rector is an extremely compact area with a capability of providing a very high heat output. Regardless of the type of coolant used, the heat transfer characteristics of this region must be adequately designed to prevent any undesirable "hot-spots" from developing. The Sandia Engineering Reactor has one of the most compact cores of any in currently operating nuclear reactors. For this reason it is necessary to investigate fully the heat transfer characteristics of the core. The rate of heat transfer from the fuel elements to the coolant is directly dependent upon the temperature difference between the fuel elements and the coolant, the area available for the heat transfer, and the rate of coolant flow past the fuel elements. Because of these factors an investigation of the flow of coolant was deemed necessary.
- Published
- 1960