Abstract
An experimental study has been made of the radial thermal neutron density distribution inside tubular natural uranium fuel elements containing the organic coolant—monoisopropyldiphenyl. Using the activation method, the thermal neutron density distribution has been measured in 23 different versions of the fuel element. Theoretical neutron density distributions were obtained for these fuel elements by solving the one-velocity kinetic equation on an electronic computer. The experimental and theoretical results obtained for the neutron density distributions, shielding factors and the neutron density discontinuities at the outer coolant layer are presented in the form of graphs.
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Schedule a callMore From: Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology
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