Document Details


Title:
Health Physics Division Annual Progress Report for Period Ending July 31, 1959
Subject Terms:
Clinch River Studies; Operation Hardtack II; annual progress report; cesium, strontium, sintering; complexing, disposal; ion exchange, physics; radiation physics, dosimetry; uranium, ecosystem, forest; waste, ORNL, radioactivity
Document Location:
DOE INFORMATION CENTER 1 Science.gov Way, Oak Ridge, TN 37831; Eva Butler; Phone: 865-241-4780; Toll-Free: 800-382-6938, Option 6; FAX: 865-574-3521; Email: doeic@oro.doe.gov
Document Categories:
Health, Safety and Environment\Public Health and Safety; Science and Technology\Geology, Hydrology, Seismology, Site Studies
Document Type:
REPORT
Publication Date:
1959 Jul 31
Declassification Status:
Never classified
Document Pages:
114
Accession Number:
ORF65930
Document Number(s):
ORNL-2806, TID-4500; 15th edition; 15thedition
Originating Research Org.:
Atomic Energy Commission
OpenNet Entry Date:
1998 Jun 16
Description/Abstract:
This document contains the Health Physics Division Annual Progress Report for the period ending July 31, 1959. The amount of radioactivity released to White Oak Creek from ORNL during 1958 was the lowest annual discharge on record. An experimental procedure was initiated for discovering the optimum combination of four treatment variables for removal of Cs-137 and Sr-90 from process wastes. There was a significant increase in the amounts of Sr-90 and total rare earths (TRE) in 1958. The U.S. Geological Survey is investigating several possible sites for the burial of low-level radioactive wastes in the eastern United States. The general chemical characteristics of the White Oak Lake bed soils showed little change over the last year, the pattern of vegetation increased in complexity, and the sampling regimen for insects on vegetation of the lake bed was continued. A study of natural vegetation provides information needed for predicting the future movements of isotopes in natural ecosystems, particularly forests. Two methods of using clays to contain fission product wastes were investigated. The problem with disposal of radioactive waste into natural salt formations was studied. The disposal of waste into deep wells was further investigated, and laboratory studies included the complexing of Purex, Darex, and SIR wastes; sequestering agents showed promise as a treatment for waste prior to injection into geologic formations. During Operation Hardtack II (fall of 1958) a detailed study was made of the neutron and gamma radiation dose distributions in facsimiles of typical Japanese dwellings exposed to nuclear bomb radiation. A neutron Monte Carlo code was modified to yield information pertinent to the Ichiban experiments. The study of radiation effects on the ferroelectric properties of Rochelle salt is nearly complete. The development of the wrist dosimeter led to further consideration of the design principles of ion chamber-electrometer dosimeters, and the results were summarized. Molded B-10 spherical shields were developed to replace the spherical boron-loaded shields used with fission foil threshold detectors. To obtain sufficient sensitivity to measure the P-32 activity in the sulfur detector in the event of an incident, a low-background scintillation counter was developed. A gamma dosimeter was being developed with the Phillips 18509/01 miniature halogen-filled Geiger counter. Data from dogs exposed to single inhalations of U-3 O-8 fumes indicated a biological half-life in the lung of about 100 days, and was estimated that the half-life of insoluble uranium compounds in the lung to be between 50 and 200 days. Studies were initiated to determine more accurately the retention, distribution, and excretion of uranium in chronic exposure cases. An inhalation chamber for the exposure of mice to radioactive aerosols is under development. The study of the deposition of soluble uranium compounds in the animal body was extended to an additional species, female white rats. A special scintillation counter for measuring the radioactivity of small animals and other samples was developed. Analysis of human tissue by emission spectroscopy and flame photometry continued. Figures and tables are included.


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