Salt Bath Heat Transfer Rates for Uranium Plate (open access)

Salt Bath Heat Transfer Rates for Uranium Plate

Experiment to study temperature conditions during a five-minute heating cycle in the annealing of uranium sheets used as fissile material.
Date: February 1, 1962
Creator: Burditt, R. B.
System: The UNT Digital Library
Multi-Channel Boiling Stability for Sodium Graphite Reactors (open access)

Multi-Channel Boiling Stability for Sodium Graphite Reactors

Abstract: This report presents an analysis of coolant boiling in sodium graphite reactors.
Date: March 1, 1962
Creator: Cappel, H. H.
System: The UNT Digital Library
Thermal Stress Testing of Beryllium Oxide Moderator Shapes (open access)

Thermal Stress Testing of Beryllium Oxide Moderator Shapes

Abstract: Perforated BeO plates were thermal shock tested to evaluate the effect of: (1) localized temperature variations adjacent to the perforations, and (2) radial gradients across the entire plate.
Date: August 1, 1962
Creator: Sujata, H. L.; King, M. & Waters, F. J.
System: The UNT Digital Library
Evaluation of Zirconium Hydride as Moderator in Integral, Boiling Water-Superheat Reactors (open access)

Evaluation of Zirconium Hydride as Moderator in Integral, Boiling Water-Superheat Reactors

This report summarizes the results and conclusions of a study made to evaluate the merits of using zirconium hydride as a solid moderator in an integral boiling water-nuclear superheat reactor of the pressure vessel type.
Date: March 1, 1962
Creator: Gylfe, J. D.; Rood, H.; Greenleaf, J.; Balkwill, K.; Prem, L. & Goldfisher, L.
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1962 - September 1, 1962 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1962 - September 1, 1962

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: October 1, 1962
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Collins, William R., Jr.
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1961 - March 1, 1962 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1961 - March 1, 1962

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: April 1, 1962
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1962 - June 1, 1962 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1962 - June 1, 1962

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: July 1, 1962
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
System: The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses; First Quarterly Report, (December 1961 - February 1962) (open access)

Accurate Nuclear Fuel Burnup Analyses; First Quarterly Report, (December 1961 - February 1962)

The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date: April 1, 1962
Creator: Rider, B. F.
System: The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses; Second Quarterly Progress Report, (March - May 1962) (open access)

Accurate Nuclear Fuel Burnup Analyses; Second Quarterly Progress Report, (March - May 1962)

The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date: July 1, 1962
Creator: Rider, B. F.
System: The UNT Digital Library