Document Details

Health Physics Division Quarterly Progress Report for Period Ending October 20, 1951
Morgan, K Z [ORNL, Carbide and Carbon Chemicals Co., Oak Ridge]
Subject Terms:
Barium-137, radiochemical; Cd-115, radioactive waste; Clinch River, Tennessee River; Iodine-131, Cesium-137; White Oak Creek; ecological study, Co-60; health physics, ORNL; ionization, beta, plutonium; physics, nuclear radiation; quarterly progress report; waste decontamination
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; Science and Technology\Geology, Hydrology, Seismology, Site Studies
Document Type:
Publication Date:
1951 Oct 20
Declassification Status:
Never classified
Document Pages:
Accession Number:
Document Number(s):
ORNL-1174; Copy 17, Series A; Copy17SeriesA
Originating Research Org.:
Union Carbide and Carbon Corporation
OpenNet Entry Date:
1998 Jun 16
This document contains the Health Physics Division Quarterly Progress Report for the period ending October 20, 1951. The construction and installation of major equipment of the Health Physics Waste Research Building has been practically completed during this period, and this facility is to be occupied early in November 1951. Laboratory studies were made of the removals of tracer quantities of Ce-137 and of Cd-115 from water using conventional water treatment processes, and results were discussed. A survey was made of the intensity of radiation from bottom deposits in the river and lakes below White Oak Creek by means of a "flounder," a water-and sediment-scanning instrument; a preliminary review indicated slight elevations above background radioactivity in the bottom sediments except where water velocities had scoured the bottom clean. Collision densities and energy losses of a monoenergetic beam of neutrons normally incident on an infinite slab of tissue of 30 cm thickness were obtained by means of a Monte Carlo procedure, and the results were summarized. Experiments were concluded on the absorption of the internal conversion electrons from Ba-137 in various thicknesses of materials of several atomic numbers. A method of weighting pulses by their height was developed in cooperation with the Instrument Department. A series of flights over sources of Na-24, Co-60, Cs-137, Ra, and Ta-182 were made at heights from a few hundred feet to, in some cases, more than 3000 feet, and the variation of gamma-ray response of the NaI-crystal scintillometers indicated a buildup factor roughly proportional to the altitude. Preliminary calculations of maximum permissible concentrations of radioisotopes in total body, in air, and in water were made for 35 additional isotopes, largely fission products, and these calculations were included. Open-air measurements were made of a large 300-curie cobalt source to be used for cancer therapy, and preliminary examination found this procedure to be grossly inaccurate due to limited information concerning the buildup factor introduced by air-and ground-scattering. Figures and tables are included.

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