Fast-Neutron Flux Measurements in the ORNL Graphite Reactor Shield
Description:
In a study of the nuclear and physical properties of the concrete shield of the ORNL Graphite Reactor measurements were made of the fast-neutron fluxes in a hole through the shield. These fluxes were not incinded in the formal report of the study (ORNL-2195) since several uncertainties associated with the measurements made the absolute values unreliable. The attenuation curves at one energy may be reasonably accurate, however. (auth)
Date:
August 14, 1958
Creator:
Blosser, T. V.; Bond, G. W.; Lee, L. A.; Morgan, D. T.; Nichols, J. F.; Reid, R. C. et al.
Item Type:
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Report
Partner:
UNT Libraries Government Documents Department