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Further Critical Experiments on a Small Reactor of Enriched U-235 with Al-H₂O Moderator and Beryllium Reflector

Description: From introduction: "The purpose of the present report is to describe briefly certain improvements that have been made in the experimental facilities and to present the results of further measurements on critical masses and spatial neutron flax distributions in Be reflected reactors having square and thin slab geometries."
Date: August 17, 1948
Creator: Martin, A. B. & Mann, M. M.
Partner: UNT Libraries Government Documents Department
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Monitoring Thermal and Resonance Neutron Flux

Description: The monitoring of thermal and resonance neutron flux in a thermal reactor having high flux over periods of time from 1 to 12 months using think Co foils is considered. Special attention is paid to the many correction factors to be applied to the activation data; neutron temperature, effective cadmium cutoff energy, burnout of Co59 and Co60, and decay of Co60. Results on a homogeneity test of 10 mil, 0.08% Co-A1 alloy foils is given.
Date: August 17, 1953
Creator: Heineman, R. E.
Partner: UNT Libraries Government Documents Department
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