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Television System Study for Accident Recovery : Phase I

Description: From abstract: "A previous study of equipment necessary for clean-up following a nuclear accident indicated a need for a portable television system capable of operating in hazardous environments during recovery operations. A system to accomplish this is described and justified in this study."
Date: April 1966
Creator: Talpis, N. A. & Burge, D. L.
Partner: UNT Libraries Government Documents Department
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Post-Test Physical, Chemical and Metallurgical Analysis of SNAPTRAN-3 Fuel

Description: The fuel element damage which occurred during the SNAPTRAN-3 Destructive Test of a Snap 10A/2 reactor is described. Chemical analysis of the fuel indicated that approximately 15% of the hydrogen was released and that the core flux was higher toward the center both radially and axially. Metallurgical analysis of the fuel determined the presence of the epsilon, delta, and gamma phases in the grain structure and evidence of a possible alpha or beta phase.
Date: June 1965
Creator: Fletcher, R. D.
Partner: UNT Libraries Government Documents Department
open access

Addendum to the Spert IV Hazards Summary Report: Capsule Driver Core

Description: From abstract: "explain all important features pertaining to a new pulsed irradiation reactor, the Capsule Driver, Core, and to analyze the potential problems and hazards of operating this reactor in the existing Spert IV facility."
Date: February 1965
Creator: Miller, R. W.; McCardell, Richard K. & Lagier, T. F.
Partner: UNT Libraries Government Documents Department
open access

Radiological Aspects of SNAPTRAN 2/10A-3 Destructive Test

Description: From abstract: "This report describes in detail an extensive monitoring grid used to monitor the radiological effects of the destructive excursion and subsequent release of fission products."
Date: January 1965
Creator: Cordes, O. L.; Bird, R. P.; Dinneen, G. A. & Fielding, J. R.
Partner: UNT Libraries Government Documents Department
open access

An Engineering Test Program to Investigate a Loss of Coolant Accident

Description: From preface: "The purpose of this report is to present an engineering test program for investigating a loss of coolant accident for a pressurized water-cooled and moderated reactor system."
Date: October 1964
Creator: Wilson, T. R.; Hauge, O. M.; Matheney, G. B. & Homer, G. B.
Partner: UNT Libraries Government Documents Department
open access

Gamma-Ray Spectrometry of Neutron-Deficient Isotopes: Annual Progress Report, March 1964

Description: From abstract: "The objective of this program is to produce a set of pulse-height spectra representing the response of a standard gamma-ray scintillation spectrometer to radiations emitted in the decay of neutron-deficient nuclides."
Date: March 27, 1964
Creator: Heath, R. L. & Cline, J. E.
Partner: UNT Libraries Government Documents Department
open access

Advanced Test Reactor Servo Regulator Rod Test Program

Description: From abstract: "Verify rod mechanism characteristics reported by the United Shoe Machinery Corporation, demonstrate that rod mechanism characteristics were compatible with reactor kinetics and that over-all reactor system behavior was stable, and to recommend system modifications needed for satisfactory performance."
Date: February 1964
Creator: Pickett, R. T., III
Partner: UNT Libraries Government Documents Department
open access

Advanced Test Reactor Turbo Report

Description: From abstract: "The time-dependent behavior of the Advanced Test Reactor was calculated by the Babcock & Wilcox Company on the Philco 2000 computer, using the Turbo depletion program."
Date: January 1964
Creator: Turner, Robert A.
Partner: UNT Libraries Government Documents Department
open access

Advanced Test Reactor: Final Shielding Design Report

Description: From abstract: "This report has been prepared as a design reference document describing the calculation methods and engineering results for shielding analysis work done during the design of the Advanced Test Reactor."
Date: December 1963
Creator: Howard, J. O. & Jacks, G. M.
Partner: UNT Libraries Government Documents Department
open access

Fundamentals in the Operation of Nuclear Test Reactors: Volume 2, Materials Testing Reactor Design and Operation

Description: Second volume of reports on the operation of nuclear test reactors. It includes six chapters: engineering description fo the materials testing reactor, reactor control components and instrumentation, reactor control circuitry, reactor operation, reactor shutdown and tank work, and supplemental facilities at the materials testing reactor.
Date: October 1963
Creator: Phillips Petroleum Company
Partner: UNT Libraries Government Documents Department
open access

EDP Procedures in Technical Library Operations

Description: Systems for circulation control, book ordering, journal renewal, printing a book catalog, preparing monthly acquisitions lists.
Date: July 30, 1963
Creator: Griffin, Hillis L.
Partner: UNT Libraries Government Documents Department
open access

The Design of a Dynamic Corrosion and Chemical Control Test Loop and Preliminary Out-of-Pile Test Results

Description: From abstract: "This report describes the overall loop design and the means by which this design was developed. These include critical facility measurements, analog computer calculations, hydraulic and heat transfer computations, and the construction and operation of an out-of-pile mock-up loop to determine the dynamic characteristics of the loop."
Date: July 12, 1963
Creator: Zelezny, W. F.
Partner: UNT Libraries Government Documents Department
open access

High-Temperature Irradiation of UOâ‚‚-BeO Bodies

Description: From introduction: "Irradiation experiment performed to simulate burnup data under close to reactor temperatures."
Date: January 1963
Creator: Titus, G. W. & Saling, J. H.
Partner: UNT Libraries Government Documents Department
open access

EOCR Control Rod and Driver Fuel Hydraulic Tests

Description: Report discussing the results of experiments on an EOCR prototype control rod, control rod drive, and driver fuel assembly that were extensively tested in 500 deg F Santowax and 132 deg F water. These tests not only established the operating characteristics of these assemblies but also revealed a number of deficiencies in the various components. It includes descriptions of the control rod, control rod drive, and driver fuel assembly together with descriptions of their method of operation.
Date: October 19, 1962
Creator: Harrison, L. J.
Partner: UNT Libraries Government Documents Department
open access

Engineering Test Reactor Critical Facility Control System Manual

Description: This report consists of the description, drawings, connections, and schematics of the various control elements that make up the control system of the Engineering Test Reactor Critical Facility (ETRC).
Date: June 23, 1961
Creator: Meichle, F. A.
Partner: UNT Libraries Government Documents Department
open access

In-Pile Tests of GCRE-IB Prototype Fuel Elements: Interim Report, 1958-1959

Description: Interim report for the Army Gas-Cooled Reactor Systems Program, discussing various tests in a project to "develop and evaluate a ceramic-core, pin-type fuel element" (p. 1).
Date: December 1960
Creator: Watanabe, H. T.; Janne, J. E. & Wilson, W. D.
Partner: UNT Libraries Government Documents Department
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