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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
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An Elliptic Integral Computer Package for Magnetic Fields, Forces, and Mutual Inductances of Axisymmetric Systems, and a Versatile Line-Tracing Routine

Description: Report describing a set of high-precision routines for the IBM 7090 that perform efficiently the calculations most often required on axially symmetric magnetic systems. The routines compute the vector potential, field components, and the mixed gradient for current systems and for certain idealized distributions of magnetized matter. The programs for the current systems were developed from a set of six equations in elliptic integrals, which suffice when correlations are fully exploited for all the relevant properties of loops and solenoids.
Date: April 1965
Creator: Garrett, M. W.
Partner: UNT Libraries Government Documents Department
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Fast Flux Test Facility Studies Progress Report: April 1965

Description: From abstract: "...limited study work was performed on the conceptual design of the proposed fast flux test facility and information was obtained in important areas of supporting technology."
Date: April 1965
Creator: Astley, E. R.
Partner: UNT Libraries Government Documents Department
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Flow-Regime Transitions at Elevated Pressures in Vertical Two-Phase Flow

Description: Two-phase flow-regime transitions at elevated pressures for a single-component, trichloromonofluoromethane, were investigated for forced-circulation, upward flow in a vertical, rectangular conduit with internal dimensions of 0.380 by 1.050 inches.
Date: September 1965
Creator: Baker, James L. L.
Partner: UNT Libraries Government Documents Department
open access

Irradiation Effects in the EGCR Fuel

Description: From foreword: "This is a documentation of the experiments performed and the data accumulated during the early period of the Experimental Gas-Cooled Reactor (EGCR) fuel element design."
Date: June 1965
Creator: Baumann, C. D.
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

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

A Sequence for Predicting Waste Transport by Ground Water

Description: From introduction: "This paper describes a sequence for analyzing the effects of ground water flow on waste transport in natural soils."
Date: April 15, 1965
Creator: Nelson, R. William
Partner: UNT Libraries Government Documents Department
open access

Static Tests of Corrosion Inhibitors for Aluminum and Carbon Steel

Description: The experiments described in this report were performed for two purposes: (1) to find a chemical, or combination of chemicals, that would be effective for inhibiting corrosion of steel in static portions of the Hanford water systems, and (2) as screening tests to select candidate mixtures for further testing to replace sodium dichromate as the inhibitor of aluminum and steel corrosion in the Hanford single-pass reactor cooling water.
Date: February 1965
Creator: Richman, R. B.
Partner: UNT Libraries Government Documents Department
open access

A Study of Convective Magnetohydrodynamic Channel Flow

Description: Analysis of a class of steady magnetohydrodynamic channel flow problems when natural, as well as forced, convection is important.
Date: March 1965
Creator: Singer, Ralph M.
Partner: UNT Libraries Government Documents Department
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