Heat Transfer in a Cross Flow Nuclear Reactor
- 1 November 1958
- journal article
- research article
- Published by Taylor & Francis in Nuclear Science and Engineering
- Vol. 4 (5) , 607-622
- https://doi.org/10.13182/nse58-a25551
Abstract
The heat transfer between mutually perpendicular fuel and coolant channels of a nuclear reactor is studied for both isotropic and anisotropic conducting media. By means of an electrical conduction analog, a characteristic length of a unit cell of the reactor is experimentally determined for channels of rectangular and circular cross section. Empirical expressions for this characteristic length are given which closely fit the experimental data. A finite difference calculation is used to determine the temperature distribution within a unit cell.Keywords
This publication has 1 reference indexed in Scilit:
- Heat Conduction in Internally Cooled Nuclear ReactorsNuclear Science and Engineering, 1958