Energy Transfer by Neutrons to Certain Materials [electronic resource].
- Published:
- Washington, D.C. : United States. Dept. of Energy, 1965.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Additional Creators:
- Sandia National Laboratories, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Summary:
- What is attempted here is to compute the energy absorbed in several elements from interactions with neutrons in the energy range of 0 to 14 Mev. In these calculations the results have been normalized to one neutron per square centimeter incident per gram of target material, thus making it a simpler matter to calculate energy absorbed in compounds containing these elements. In these calculations the single-collision approximation is assumed in that each neutron is considered to undergo only one collision in the sample, that scattered neutron escaping from the sample. The results are presented graphically for the elements hydrogen, carbon, nitrogen; oxygen: ·aluminum, ·silicon, germanium, tantalum, and bismuth. Plotted in these figures is the energy transferred per gram of target material per single neutron per square centimeter incident as a function of the-incident neutron energy.
- Report Numbers:
- E 1.99:scr65948
scr65948 - Subject(s):
- Note:
- Published through SciTech Connect.
07/01/1965.
"scr65948"
Buckalew, W. H. - Funding Information:
- AT(29-1) 789
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