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- Title
Study of neutron spectra emitted by moderated 241Am–Be source for various moderating materials by using simulation technique.
- Authors
Kumari, N. Sujatha; Sathian, V.; Ghodke, S. S.; Singh, Yashoda; Mahant, A. K.; Ganesan, S.
- Abstract
A study was done on the tailored neutron energy spectra of 241Am–Be neutron source due to the effect of moderators. The 241Am–Be laboratory neutron source was used as the basic source and the emitted spectrum was modified using various neutron moderators. The various moderators used are high-density polythene, light water, heavy water, graphite, 56Fe, BeO, Be, 6Li and 7Li. The absolute energy spectra and fluences in each case are calculated by using the Monte Carlo code FLUKA. This paper describes the simulation work done to design a moderated 241Am–Be neutron source to produce various energy neutron spectra.
- Subjects
NEUTRON sources; RADIATION sources; REACTOR moderators; MONTE Carlo method; GRAPHITE
- Publication
Radiation Protection Dosimetry, 2012, Vol 150, Issue 1, p96
- ISSN
0144-8420
- Publication type
Article
- DOI
10.1093/rpd/ncr363