ISSN:
1573-8205
Source:
Springer Online Journal Archives 1860-2000
Topics:
Energy, Environment Protection, Nuclear Power Engineering
,
Physics
Notes:
Abstract The neutron moderation length is an important constant without which is is impossible to deal with the design of nuclear reactors in all their aspects. A knowledge of the moderation lengths is especially necessary for the determination of the space distribution of the neutrons in a reactor, and for the calculation of the energy spectrum of the moderated neutrons. In the present work is given an approximate solution of the integral equations satisfied by the space moments of the neutron distribution function inan infinite medium with an infinite, plane, isotropic source. The energy-angle moments of the neutron scattering function are expressed in terms of experimentally determined angular distributions of neutrons of various energies in the case of anisotropic elastic scattering from nuclei. By using experimental results for the total cross section and for the angular distribution in the case of elastic scattering from the nuclei H1, D2, Be9, C12, O16 the neutron moderation lengths were calculated for the moderators: water, heavy water, graphite, beryllium, and beryllium oxide. The results of the calculation were found to be in satisfactory agreement with experimental values.
Type of Medium:
Electronic Resource
URL:
http://dx.doi.org/10.1007/BF01471920
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