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

Description: 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.

Breeding-Gain Specimens for EBR-I Core IV

Description: Report issued by the Argonne National Laboratory over studies conducted on uranium and plutonium specimens used in fuel rods. The results are presented and discussed. This report includes tables, illustrations, and photographs.
Date: September 1963
Creator: Shuck, A. B.; Hins, A. G.; Burt, W. R. & Beatty, R. A.

Testing of Containment Capabilities of Reinforced Concrete-Shielded Enclosures

Description: From Summary: "The strains in the walls and ceiling of Cell No. 5 were recorded with 39 SR-4 strain gages strategically placed on reinforcing steel. Table I summarizes the comparative results without including correction for stress concentrations. The general pattern of cell behavior at 10 psig, as summarized in Table I, is shown in Figs. 10, 11, 12."
Date: March 1963
Creator: Fistedis, S. H.; Heineman, A. H. & Janicke, M. J.

A Performance Analysis of the EBWR at Various Power Levels

Description: From Introduction: "This study is an attempt to predict the operating performance of EBWR (Experimental Boiling Water Reactor) at various power levels. It was done at the same time that EWBR was raised in power up to 100 MW, and so an excellent possibility was given to check the validity of the used performance analysis. Rather than giving a general and complete outline of the analysis or establishing a new approach, the study outlines and specifies the numerous practical problems involved in this analysis, and tries to explain the discrepancies between predicted and experimental results."
Date: October 1963
Creator: Nentwich, Alfred A.

Dynamic Analysis of Coolant Circulation in Boiling Water Nuclear Reactors

Description: Report concerning the study of the two-phase flow through the cooling channels of a natural-circulation boiling water nuclear reactor. "One-dimensional conservation equations describing the flow through each channel are written in the linearized perturbed form, and Laplace transformation in time is performed." (p. 5)
Date: April 1964
Creator: Sanathanan, Chathilingath K.

A Practical Approach to Availability and Irreversibility

Description: From Introduction: "The purpose of this paper is to shed additional light on the techniques of a Second Law Analysis. The stimulus for writing this paper came from questions asked and difficulties that occurred during lectures on the subject at the graduate level. This paper utilizes Keenan's basic approach but presents the material with emphasis upon a clear definition of the work associated with each subsystem in the process."
Date: June 1963
Creator: Hoglund, Barton M.

The Period Effect in Reactor Dynamics

Description: From Abstract: "An alternative approach is presented with attempts to demonstrate that insight may be gained from a consideration that the basic cause of the effect may be due to reactivity rather than to period as the previous authors assumed. Methods for compensating for this effect are discussed."
Date: April 1964
Creator: Carter, Joseph C.; Sparks, David W. & Tessier, Jack H.

Recrystallization in Rolled Uranium Sheet

Description: From Introduction: "To overcome the difficulties another investigation has been carried out wherein the rolling stock was subjected to step reduction and annealing treatments designed to develop a small, uniform grain size prior to the final rolling at room temperature. The results of metallographic, dilatometric, and X-ray diffraction studies of this material are given."
Date: March 1962
Creator: Lloyd, Lowell T. & Mueller, Melvin H.

Preliminary Design of a Basic Radiation Effects Reactor (BRER)

Description: From Introduction: "Information has been accumulated about the property changes produced, but there are essentially no reliable quantitative data correlating property changes with the magnitude and energy distribution of the neutron fluxes responsible for the changes. The design of the Basic Radiation Effects Reactor (BRER) presented herein stems from the two main requirements: 1. a fairly high-level, high-energy neutron flux with minimal thermal neutron and gamma-ray background is desired; 2. the peak of the neutron-energy spectrum should be variable within the approximate range from 10 to 1000 kev."
Date: March 1961
Creator: MacFarlane, D. R.; Rohde, R. R.; Toppel, B.; Charak, I. & Unger, H.

Terminal Report on the Mighty Mouse High-Flux Research Reactor Project

Description: From Introduction: "More specifically, it describes the basic reactor complex, the problems involved, the various approaches pursued, the present status and estimated cost of the project, along with recommendations for future research and development essential to the successful culmination of the project."
Date: September 1959
Creator: Link, L. E.; Armstrong, R. H.; Cameron, T. C.; Dickson, R. F.; Heineman, J. B.; Kelber, C. N. et al.

Casting and Fabrication of Core Material For Argonne Low Power Reactor Fuel Elements

Description: Report issued by the Argonne National Laboratory over studies conducted on the Argonne Low Power Reactor. As stated in the abstract, "this report describes the manufacture of 1150 fuel core blanks, of which 816 were used in the fabrication of fuel elements. Development, casting, hot and cold rolling, cleaning, and punching of core blanks are discussed, as are nondestructive testing and evaluation of the manufacturing processes" (p. 7). This report includes tables, illustrations, and photographs.
Date: December 1959
Creator: Salley, R. L. & Burt, W. R., Jr.

Design Summary Report on the Juggernaut Reactor

Description: Report issued by the Argonne National Laboratory over design studies conducted on the Juggernaut reactor. Design processes, and methods are presented and discussed. This report includes tables, illustrations, and photographs.
Date: September 1962
Creator: Folkrod, J. R.; Ember, G.; Kolb, W.; Saluja, J. & Moon, D. P.