Errata for ANL-6628: Automatic Foil Activity Counting Facility and Data-Reduction Program (open access)

Errata for ANL-6628: Automatic Foil Activity Counting Facility and Data-Reduction Program

Errata sheet listing corrections to three pages of a report that describes a transistorized automatic counting and recording system built for the determination of foil-activation data.
Date: April 8, 1963
Creator: Glassner, Alvin
Object Type: Text
System: The UNT Digital Library
Reactor Development Program Progress Report: March 1963 (open access)

Reactor Development Program Progress Report: March 1963

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during March 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: April 15, 1963
Creator: Adams, R. M. & Glassner, A.
Object Type: Report
System: The UNT Digital Library
Reactor Development Program Progress Report: April 1963 (open access)

Reactor Development Program Progress Report: April 1963

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during April 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: May 15, 1963
Creator: Adams, R. M. & Glassner, A.
Object Type: Report
System: The UNT Digital Library
Description and Proposed Operation of the Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II) (open access)

Description and Proposed Operation of the Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II)

Report regarding "[t]he Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II), the process equipment, and the operations to be conducted in the facility are described. The Fuel Cycle Facility is a plant for reprocessing, by pyro-metallurgical methods, the core and blanket material discharged from EBR-II. The reactor core alloy is uranium-5 percent fissium and contains about 46 wt.% Uranium-235 . The blanket material consists of uranium in which plutonium is bred. Core and blanket subassemblies contained in transfer coffins are transferred between EBR-II and the Fuel Cycle Facility, which is in an adjacent building." (p. 13)
Date: April 1963
Creator: Hesson, J. C.; Feldman, M. J. & Burris, L.
Object Type: Report
System: The UNT Digital Library
Safety Analysis Report, Argonne Fast Critical Facility (ZPR-VI) (open access)

Safety Analysis Report, Argonne Fast Critical Facility (ZPR-VI)

Report by the Argonne National Laboratory evaluating the Argonne Fast Critical Facility, ZPR-VI, under construction during the course of the study. The study addresses various functionalities and safety features of the facility.
Date: December 1963
Creator: Kato, W. Y.; Fischer, G. J. & Dates, L. R.
Object Type: Report
System: The UNT Digital Library
Fabrication of UO2-Stainless Steel Dispersion Fuel For Borax-V Nuclear Superheat (open access)

Fabrication of UO2-Stainless Steel Dispersion Fuel For Borax-V Nuclear Superheat

Report describing the development, fabrication, and nondestructive and destructive evaluation of stainless steel-clad fuel plates, the evaluation of fuel subassemblies, and the assembly of fuel element components at Argonne National Laboratory.
Date: December 1963
Creator: Kramer, W. C. & Bean, C. H.
Object Type: Report
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.
Object Type: Report
System: The UNT Digital Library
Breeding-Gain Specimens for EBR-I Core IV (open access)

Breeding-Gain Specimens for EBR-I Core IV

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.
Object Type: Report
System: The UNT Digital Library
Testing of Containment Capabilities of Reinforced Concrete-Shielded Enclosures (open access)

Testing of Containment Capabilities of Reinforced Concrete-Shielded Enclosures

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.
Object Type: Report
System: The UNT Digital Library
A Survey of Prompt-Neutron Lifetimes in Fast Critical Systems (open access)

A Survey of Prompt-Neutron Lifetimes in Fast Critical Systems

From Introduction: "Los Alamos and British lifetime measurements are consistent with the results reported here."
Date: August 1963
Creator: Brunson, G. S.; Curran, R. N.; Gasidlo, J. M. & Huber, R. J.
Object Type: Report
System: The UNT Digital Library
Thermal Hydraulic Performance Characteristics of EBWR (0 to 100 Mwt) (open access)

Thermal Hydraulic Performance Characteristics of EBWR (0 to 100 Mwt)

From Introduction: "As a result, the modification of the EBWR internals for operation at higher power was directed primarily toward achieving this goal. The major modifications that were made are described briefly below."
Date: May 1963
Creator: Petrick, Michael & Spleha, E. A.
Object Type: Report
System: The UNT Digital Library
Interim Report: Faret Experimental Program (open access)

Interim Report: Faret Experimental Program

From Introduction: "The Fast Reactor Test (FARET) program is part of the United States Fast Reactor Program directed toward the demonstration of breeder reactors essential to the long-range goal of utilizing fertile fuels. (1) With-in this program is the current thinking that the early construction and operation of two or three prototype nuclear power plants of the order of 250 Mw(e) will lead eventually to the construction of practical and economic full scale breeder reactors by the early 1980's. (2)"
Date: April 1963
Creator: Smaardyk, A.; Bump, T. R.; Handwerk, J. & Handwerk, J.
Object Type: Report
System: The UNT Digital Library
Transient Behavior of a Natural-Circulation Loop Operating Near The Thermodynamic Critical Point (open access)

Transient Behavior of a Natural-Circulation Loop Operating Near The Thermodynamic Critical Point

From Introduction: "Interest in utilizing natural-circulation loops to obtain results that aid in the design of some boiler and nuclear reactor coolant systems has focused attention on the dynamic behavior of such loops. Much analytical and experimental work has been done so as to permit predictions of the transient behavior of both single-phase and two-phase neutral-circulation systems. The analytical portion of the study consisted of simulating the loop by utilizing a digital computer to predict the measured transients."
Date: May 1963
Creator: Harden, Darrel G.
Object Type: Report
System: The UNT Digital Library
Heat Transfer, Flow Instability, and Critical Heat Flux For Water in a Small Tube At 200 psia (open access)

Heat Transfer, Flow Instability, and Critical Heat Flux For Water in a Small Tube At 200 psia

From Abstract: Report discussing "the effects of developing two-phase flow regimes in a constant-pressure drop system are shown in recorded traces from a fast-response flow transducer: the mass velocity decreases and transfer-surface superheat increases with increasing steam quality."
Date: June 1963
Creator: Weatherhead, R. J.
Object Type: Report
System: The UNT Digital Library
A Performance Analysis of the EBWR at Various Power Levels (open access)

A Performance Analysis of the EBWR at Various Power Levels

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.
Object Type: Report
System: The UNT Digital Library
Development of an Electrical Resistivity Probe For Void-Fraction Measurements in Air-Water Flow (open access)

Development of an Electrical Resistivity Probe For Void-Fraction Measurements in Air-Water Flow

"Work has been done on the adaptation of an electrical probe, developed by Neal for the measurement of local void fractions in mercury-nitrogen flow, to air-water flow. The adaptation is more difficult because of wetting of the probe by water. Various probe shapes and filming agents were employed without great success" (p. 1).
Date: June 1963
Creator: Nassos, George P.
Object Type: Report
System: The UNT Digital Library
A Practical Approach to Availability and Irreversibility (open access)

A Practical Approach to Availability and Irreversibility

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.
Object Type: Report
System: The UNT Digital Library
Two-Phase Critical Flow With Application to Liquid-Metal Systems (Mercury, Cesium, Rubidium, Potassium, Sodium, and Lithium) (open access)

Two-Phase Critical Flow With Application to Liquid-Metal Systems (Mercury, Cesium, Rubidium, Potassium, Sodium, and Lithium)

From Introduction: "In the present report the best available theory is utilized to calculate void fractions, slip ratios, and flow rates for liquid-vapor metal systems in pipes under critical flow conditions."
Date: October 1963
Creator: Fauske, Hans K.
Object Type: Report
System: The UNT Digital Library
An Experimental Investigation of Two-Phase, Two-Component Flow in a Horizontal, Converging-Diverging Nozzle (open access)

An Experimental Investigation of Two-Phase, Two-Component Flow in a Horizontal, Converging-Diverging Nozzle

Report that "describes an investigation of the flow characteristics in a horizontal, converging-diverging nozzle for a two-phase, two-component system" (p. 1) using air and water and "attempting to determine the effects of accelerating the liquid phase by the gaseous phase" (p. 1).
Date: July 1963
Creator: Vogrin, Joseph A., Jr.
Object Type: Report
System: The UNT Digital Library