Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility (open access)

Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility

A series of calculations are described which evaluated the heat transfer and fluid flow aspects of the Plutonium Recycle Test Reactor Pressurized Gas-Loop Facility.
Date: June 1961
Creator: Muraoka, J.
System: The UNT Digital Library
Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor (open access)

Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor

Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.
Date: June 1961
Creator: Harty, H.; Regimbal, J. J.; Toyoda, K. G. & Widrig, R. D.
System: The UNT Digital Library
Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy (open access)

Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy

This purpose of this report is to establish a means of determining the mean effective temperature at which any specimen of Al-Si had been annealed.
Date: June 1961
Creator: Todd, R. H.
System: The UNT Digital Library
Dual Channel Pulse Analyser and Count-Rate Meter for Gamma Spectrometer Monitor (open access)

Dual Channel Pulse Analyser and Count-Rate Meter for Gamma Spectrometer Monitor

Describes the current prototype model of a linear amplifier, two-channel pulse-height analyser, two-channel count-rate meter, and count-rate difference detector for a gamma-ray spectrometer monitor developed to approach the above design criteria.
Date: June 17, 1954
Creator: Paul, R. S. & Wood, M. R.
System: The UNT Digital Library
Structural Evaluation of Underground Waste Storage Tanks (open access)

Structural Evaluation of Underground Waste Storage Tanks

To set forth limiting values of internal vapor pressure and effective liquid specific gravity which will permit the maximum utilization of the existing underground waste storage capacity. It is also intended to describe briefly the elements which could contribute to ultimate failure.
Date: June 23, 1955
Creator: Smith, Edgar F.
System: The UNT Digital Library
A Martensitic Reaction for Uranium (open access)

A Martensitic Reaction for Uranium

Series of isothermal transformation studies for improvement in fabrication and reactor performance of uranium fuel elements.
Date: June 25, 1957
Creator: Bement, A. L. & Wallace, W. P.
System: The UNT Digital Library
An Alpha, Beta, Gamma Hand and Shoe Counter - Model 2 (open access)

An Alpha, Beta, Gamma Hand and Shoe Counter - Model 2

Experimental combination hand and shoe counter redesign as a compact, simplified, register readout instrument no larger than the present Five-Fold called Model 2.
Date: June 2, 1958
Creator: Spear, W. G.
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