A Process for the Recovery of Uranium From Nuclear Fuel Elements Using Fluid-Bed Drying and Volatility Techniques (open access)

A Process for the Recovery of Uranium From Nuclear Fuel Elements Using Fluid-Bed Drying and Volatility Techniques

From Summary: "The work described in this report is the application of this process to the recovery of uranium from highly enriched, low uranium-zirconium alloy plate-type fuels."
Date: November 1961
Creator: Levitz, N.; Barghusen, J.; Carls, E. & Jonke, A. A.
System: The UNT Digital Library
Status Report on the Argonne Advanced Research Reactor (open access)

Status Report on the Argonne Advanced Research Reactor

From Introduction: "This is a status report on the interim design and development for an advanced research reactor (AARR) that will produce a maximum thermal neutron flux of 5 x 10 to the fifteenth power neutrons/ (cm2) (sec). As a result, this report also contains sections covering shielding, plant layout, fuel charging, maintenance, and auxiliary facilities."
Date: November 1961
Creator: Lennox, D. H.; Barts, E. W.; Batch, R. V.; Beyer, F. C.; Jorgensen, G. L.; Kelber, C. N. et al.
System: The UNT Digital Library
Gas-Cooled Reactors in the USA: A Survey and Recommendation (open access)

Gas-Cooled Reactors in the USA: A Survey and Recommendation

Report that provides "an understanding of the status of gas-cooled reactors as used for unclassified applications" and determining "phases of advanced research and development needed in the field and from these to recommend a program for high-temperature, gas-cooled reactors" (p. 5).
Date: November 1960
Creator: Armstrong, R. H.
System: The UNT Digital Library
Proceedings of the AMU-ANL Summer Study Program (open access)

Proceedings of the AMU-ANL Summer Study Program

From Introduction: "In 1954, the AEC presented the "five-year plan" for power reactor development, briefly outlined in Table I-1. The program proceeded and other reactors were added as a result of the incentives indicated in the outline."
Date: November 1962
Creator: Pearson, C. V.
System: The UNT Digital Library
A Method of Calculating Transient Temperatures in a Multiregion, Axisymmetric, Cylindrical Configuration the Argus Program, 1089/Re248, Written in Fortran II (open access)

A Method of Calculating Transient Temperatures in a Multiregion, Axisymmetric, Cylindrical Configuration the Argus Program, 1089/Re248, Written in Fortran II

From Abstract: "A detailed description is given of ARGUS, a FORTRAN II computer program for calculating transient temperatures in any concentric cylindrical configuration. Included are an explanation of the mathematical methods, a discussion of special features and restrictions, input and output descriptions, operating instructions, several sample problems, and the code listing."
Date: November 1963
Creator: Schoeberle, D. F.; Heestand, J.; Miller, L. B. & Miller, L. B.
System: The UNT Digital Library