ISSN:
1573-8205
Source:
Springer Online Journal Archives 1860-2000
Topics:
Energy, Environment Protection, Nuclear Power Engineering
,
Physics
Notes:
Abstract This paper is devoted to the determination of dosimetric characteristics of intermediate-energy neutrons. A calculation of the interaction of neutrons with paraffin for the normal incidence of an extended beam of neutrons in the energy interval from 100 ev to 1 Mev, which has been performed by means of an electronic computer, is given here. The computation results are used for calculating the components of the neutron tissue dose resulting from the moderation process in the tissue. The dose resulting from the neutron capture is calculated on the basis of the authors' data on the distribution of slow neutrons in paraffin and on neutron reflection from the surface of a hydrogenous medium. The depth distributions of neutron dose components for thermal neutrons and neutrons with energies of 100 ev, 1, 30, 240, 500 kev, and 1 Mev were obtained. The depth distributions of the biological dose for neutrons of the same energy and the biological dose values pertaining to the unit neutron flux were obtained.
Type of Medium:
Electronic Resource
URL:
http://dx.doi.org/10.1007/BF01472263
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