On The Steady-State Thermal Stresses in Cylindrical Fuel Pins Due to Axial Variations in Their Internal Heat-Generation Rate (open access)

On The Steady-State Thermal Stresses in Cylindrical Fuel Pins Due to Axial Variations in Their Internal Heat-Generation Rate

From Introduction: "Specifically, we shall be concerned with the case of a solid right circular cylinder of infinite axial extent, having a stress-free outer boundary, being cooled by a temperature-independent boundary conductance, and having an axial heat-generation rate of form shown in Fig. 1. The inclusion of a radial dependence proportional to I^0(r/L) is only a minor complication in solving the required heat-transfer problem and, for reference, has been included in the solution for the temperature field to be found in Section II below."
Date: December 1966
Creator: Valentin, Richard A.
System: The UNT Digital Library
XLIBIT: ANL Cross-section Library Code (open access)

XLIBIT: ANL Cross-section Library Code

From Introduction: "With the acquisition by the Laboratory of a Control Data 3600 computer in the fall of 1963, a joint reprogramming project was undertaken by the Laboratory's Applied Mathematics Division and the Control Data Corporation to develop one - and two-dimensional diffusion-theory and Sn transport-theory programs for the CDC-3600. The XLIBIT code described in this report was developed as a part of this project. XLIBIT is a CDC-3600 program designed to: 1) Prepare a cross-section library tape. 2) Modify an existing cross-section library tape. 3) Duplicate an existing cross-section library tape. 4) Print all or a portion of the cross-section data on the library tape. Punch cross-section decks for all or a portion of the data on the library tape. The decks produced are identical to those used in pertaining the tape."
Date: February 1966
Creator: Sparck, S. D.
System: The UNT Digital Library
Reactor Development Program Progress Report: May 1966 (open access)

Reactor Development Program Progress Report: May 1966

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during May 1966. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: June 30, 1966
Creator: Adams, R. M. & Glassner, A.
System: The UNT Digital Library
Reactor Development Program Progress Report: September 1966 (open access)

Reactor Development Program Progress Report: September 1966

Report issued by the Argonne National Laboratory discussing progress made within the Reactor Development Program for September, 1966. The report includes highlights of the different project activities including plutonium utilization, fast breeder reactors, general reactor technology, advanced systems research, and nuclear safety. This report includes tables, illustrations, and photographs.
Date: October 26, 1966
Creator: Adams, R. M. & Glassner, A.
System: The UNT Digital Library
A Generalized Computer Program for Flowsheet Calculation and Process Data Reduction (open access)

A Generalized Computer Program for Flowsheet Calculation and Process Data Reduction

Report issued by the Argonne National Laboratory discussing the PACER-65 computer program. As stated in the summary, the program "has been developed and utilized for flow sheet calculations and process-data reduction. PACER-65 is an executive program in which material- and energy-balance equations, conversion factors, etc., for each processing step are described by separate subroutines" (p. 5). This report includes tables, and illustrations.
Date: April 1966
Creator: Koppel, L. B.; Alfredson, P. G.; Anastasia, L. J.; Knudsen, I. E. & Vogel, G. J.
System: The UNT Digital Library