The Relative Thermal Conductivities of Liquid Lithium, Sodium, and Eutectic NaK, and the Specific Heat of Liquid Lithium (open access)

The Relative Thermal Conductivities of Liquid Lithium, Sodium, and Eutectic NaK, and the Specific Heat of Liquid Lithium

Report discussing the relative thermal conductivities of liquid lithium, sodium, and eutectic NaK, and the specific heat of liquid lithium, as well as the methods and materials used to determine this information.
Date: April 21, 1950
Creator: Yaggee, F. L. & Untermyer, Samuel, 1912-
System: The UNT Digital Library
Heat Generation in Irradiated Uranium (open access)

Heat Generation in Irradiated Uranium

Data on the heat generated in irradiated uranium represented in both curves and formulas.
Date: October 21, 1952
Creator: Untermyer, S. & Weills, J. T.
System: The UNT Digital Library
Practical Reactor Theory (open access)

Practical Reactor Theory

Derivation and basic formulas the physicist or nuclear engineer needs to do the necessary nuclear calculation for a reactor design.
Date: October 21, 1953
Creator: Webster, J. W.
System: The UNT Digital Library
Chemical Technology Division Annual Progress Report, May 31, 1961 (open access)

Chemical Technology Division Annual Progress Report, May 31, 1961

Report documenting the ongoing research and developments of the Chemical Technology Division of the Oak Ridge National Laboratory.
Date: September 21, 1961
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
System: The UNT Digital Library
A Computer Program for Determining First-Collision Neutron Doses (open access)

A Computer Program for Determining First-Collision Neutron Doses

Data processing program written to compute the neutron dose received by individuals exposed in a nuclear excursion.
Date: May 21, 1962
Creator: McMurray, C. S.
System: The UNT Digital Library
Hazards Report for PM-2A Core II (open access)

Hazards Report for PM-2A Core II

Abstract: This technical report describes the changes incurred in the PM-2A by the planned insertion of PM-2A Core II and the replacement of the startup and check sources. PM-2A Core II components were fabricated to specifications very nearly identical to those of PM-2A Core I. The essential difference in the cores is the boron loading which permits PM-2A Core II to meet a "one-stuck rod criteria" at beginning of life. This core has been subjected to a zero power experiment and loading procedures have been developed at the Alco Critical Facility. The nuclear and thermal and hydraulic characteristics are essentially identical to those of Core I and the replacement of the startup and check sources represent no increase in the potential for or magnitude of a hazardous situation.
Date: June 21, 1962
Creator: Coombe, John R. & Stephenson, L. D.
System: The UNT Digital Library