Document Details

Health Physics Division Quarterly Report for Period Ending February 28, 1949
Morgan, K Z [ORNL, Carbide and Carbon Chemicals Corp., Oak Ridge]; Morgan, K Z [ORNL, Carbide and Carbon Chemicals Corp., Oak Ridge]
Subject Terms:
instrument, ORNL; physics, slow neutron; radioisotopes, uranium; waste disposal, fast neutron
Document Location:
DOE INFORMATION CENTER 1 Way, Oak Ridge, TN 37831; Eva Butler; Phone: 865-241-4780; Toll-Free: 800-382-6938, Option 6; FAX: 865-574-3521; Email:
Document Categories:
Health, Safety and Environment\Waste Management; Specific Material\Uranium
Document Type:
Publication Date:
1949 May 19
Declassification Date:
1979 Jun 28
Declassification Status:
Document Pages:
Accession Number:
Document Number(s):
ORNL 346
Originating Research Org.:
Atomic Energy Commission
OpenNet Entry Date:
1998 Jun 16
This document contains the Health Physics Division Quarterly Report for the period ending February 28, 1949. The principal effort of the Instrument Development Group is presently directed at the development of satisfactory survey instrumentation for fast neutrons, and three possible methods of measurement being studied are: proportional counting of recoils to exclude effects of gamma radiation; fission counting; and ionization, by modifications of the Chang and Eng. The Office of Biology and Medicine of Oak Ridge Operations of the Atomic Energy Commission has coordinated discussions leading to plans for an initial ecological survey of the White Oak drainage system by a Biological Studies Section of the Health and Safety Division of the T.V.A. Progress has been made in estimating upper and lower bounds for the collision densities in tissue, and present estimates indicate that the maximum collision density is at least on the order of two times and not substantially more than four times the incident flux. A method of analysis for uranium, developed to meet the need for a method sufficiently sensitive for monitoring significant body content of U-233 was put into routine operation, and a recovery of 80 to 85 percent can be expected. Present evidence is that no one in the laboratory has as yet fixed in his system quantities of U-233 greater than the maximum permissible amount.

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