Abstract
The aim of this work is the evaluation and calculation of the heat generation and temperature rise in local ordinary concrete due to capture of thermal neutrons. The total thermal and reactor thermal neutron fluxes were measured, and the results were used to evaluate the heat generation and temperature rise in ordinary concrete. In addition, the computer code ANISN (VAX version) and neutron multigroup cross-section library EURLiB-4 were used to calculate the total thermal neutron fluxes and the heat generation and hence the temperature rise. The results were displayed in curves to show the distribution of thermal neutron fluxes and the heat generation as well as the temperature rise in the shield thickness. The results showed a good agreement between the measured and calculated values. The results showed also that the heat generation and the temperature rise have their maximum values in the first layers of the shield thickness.
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