Heat transfer in homogeneous gas-cooled reactors
Date
1958-06-02
Authors
Journal Title
Journal ISSN
Volume Title
Publisher
Melbourne University Press on behalf of The Australian Atomic Energy Commission
Abstract
The heat source distribution in a nuclear reactor is a function of neutron flux, fuel loading, and core temperature, each of which is a function of position. In certain types of solid fuel gas-cooled reactors, the fuel distribution is such that the reactor may be regarded as homogeneous. This paper describes the method of calculating the temperature distribution in the core of such a reactor. A cyclindrical core is assumed, and the variations of coolants flow and outlet temperature with radius are found. As a first approximation the dependence of neutron flux on temperature is taken to be small and the flux is assumed to have been calculated on the basis of uniform core temperature. using this flux distribution, the first core temperature distribution is found. Subsequent flux distributions can be calculated to refine the values of temperatures.
Description
Physical copies held by ANSTO Library at DDC: 539.7/348
Keywords
Heat transfer, Gas cooled reactors, Neutron flux, Temperature range, Calculation methods, Homogeneous reactors
Citation
de Vahl Davism G. (1958). Heat transfer in homogeneous gas-cooled reactors. Paper present to the Australian Atomic Energy Symposium, 1958, "Peaceful Uses of Atomic Energy In Australia", Sydney, June 2 to 6, 1958. In Australian Atomic Energy Symposium, 1958 : proceedings of a Symposium on the Peaceful Uses of Atomic Energy in Australia held in Sydney from June 2 to 6, 1958. Carlton, Victoria : Melbourne University Press on behalf of the Australian Atomic Energy Commission, (pp. 471-474).