Abstract
The results of experimental and theoretical investigations into the transmission of neutrons through hydrogen-free, uniform materials and mixtures are discussed. The relaxation lengths obtained for neutrons of different energy groups are discussed. It is shown that under certain assumptions the mag 7 nitude of the flux attenuation for neutrons of the upper energy group (En ≧ 3 MeV) in a hydrogen- free medium can be obtained from very simple empirical expressions by using well-known constants: the removal cross section Ore m, the cross section obtained from the reciprocal of the relaxation length (δ1/λ) and the asymptotic cross section δas. Values are derived for these constants.
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Translated from Atomnaya Énergiya, Vol. 18, No. 4, pp. 350–357, April, 1965
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Tsypin, S.G., Sinitsyn, B.I. & Daruga, V.K. Transmission of neutron radiation from a reactor through hydrogen-free media. At Energy 18, 442–450 (1965). https://doi.org/10.1007/BF01115963
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DOI: https://doi.org/10.1007/BF01115963