Abstract
A deuterium-tritium neutron source is amplified when emitted into a body of material with appreciable (n,2n), (n,3n), and (n,f) cross sections. This amplification is described by a simple theory, approximating the strict integral transport description of the process. The distribution of neutrons in energy, from 14 MeV down to the (n,2n) threshold, is approximated by a generalized slowing down equation, which is similar in form to the infinite medium slowing down equation, and with average collision probabilities taking up the role of scattering fractions.
Original language | English |
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Pages (from-to) | 143-152 |
Number of pages | 10 |
Journal | Nuclear Science and Engineering |
Volume | 91 |
Issue number | 2 |
DOIs | |
State | Published - 1 Jan 1985 |
ASJC Scopus subject areas
- Nuclear Energy and Engineering