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In Vivo Gamma Counting Method of Determining Uranium Lung Burden in Humans (open access)

In Vivo Gamma Counting Method of Determining Uranium Lung Burden in Humans

Scintillation spectrometry is used to measure the gamma activity from uranium for determining lung burden in the human body.
Date: June 23, 1959
Creator: Cofield, Rogers E.
System: The UNT Digital Library
Oak Ridge National Laboratory Instrumentation and Controls Division Annual Progress Report: 1958 (open access)

Oak Ridge National Laboratory Instrumentation and Controls Division Annual Progress Report: 1958

Report documenting ongoing research and development carried out by the Instrumentation and Controls Division of the Oak Ridge National Laboratory.
Date: June 24, 1959
Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.
System: The UNT Digital Library
Molten-Salt Reactor Program Quarterly Progress Report: April 1959 (open access)

Molten-Salt Reactor Program Quarterly Progress Report: April 1959

Report documenting ongoing experiments, designs, and tests undertaken by the Oak Ridge National Laboratory for the Molten-Salt Reactor Project.
Date: June 26, 1959
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Physics Division Annual Progress Report, March 10, 1959 (open access)

Physics Division Annual Progress Report, March 10, 1959

Report containing reports from the Physics Division of the Oak Ridge National Laboratory that cover a wide variety of subjects.
Date: June 10, 1959
Creator: Oak Ridge National Laboratory. Physics Division.
System: The UNT Digital Library
Final Report on Design Tests PR-50 and PR-51: Reactor Piping Seal Testing and Reactor Piping Structural Integrity (open access)

Final Report on Design Tests PR-50 and PR-51: Reactor Piping Seal Testing and Reactor Piping Structural Integrity

A test program conducted to develop high integrity piping and seal components for Plutonium Recycle Test Reactor installation. Methods of preventing leakage of costly D2O coolant and maintaining operational safety were investigated.
Date: June 26, 1959
Creator: Jackson, P. M.
System: The UNT Digital Library
Argonne High-Flux Research Reactor: AHFR Conceptual Design Study (open access)

Argonne High-Flux Research Reactor: AHFR Conceptual Design Study

Report issued by the Argonne National Laboratory discussing high-flux research reactor design studies. As stated in the summary, "this report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiation in thermal flux...and some beam experiments..." (p. 5). This report includes tables, and illustrations.
Date: June 1959
Creator: Link, L. E.; Armstrong, R. H.; Cameron, T. C.; Heineman, J. B.; Kelber, C. N.; Kier, P. H. et al.
System: The UNT Digital Library