High-Density Concrete for Gamma and Neutron Attenuation (open access)

High-Density Concrete for Gamma and Neutron Attenuation

Report issued by the Oak Ridge National Laboratory discussing the development of a high-density concrete. As stated in the abstract, "the basic approach to high-density concrete mix design is reviewed to show that theoretical calculations for concrete mixes do give results that are reliable" (p. 1). This report includes tables, illustrations, and photographs.
Date: March 1965
Creator: Northup, T. E.
System: The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965 (open access)

Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965

Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Progress of operations, construction, engineering analysis, and development is presented. This report includes tables, illustrations, and photographs.
Date: June 1965
Creator: Briggs, R. B.
System: The UNT Digital Library
A Sequence for Predicting Waste Transport by Ground Water (open access)

A Sequence for Predicting Waste Transport by Ground Water

From introduction: "This paper describes a sequence for analyzing the effects of ground water flow on waste transport in natural soils."
Date: April 15, 1965
Creator: Nelson, R. William
System: The UNT Digital Library