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Evaluated Neutron Cross Sections for Tritium

Description: From foreword: Evaluation of the experimental data on the light isotopes, hydrogen through beryllium, was initiated by LASL in mid-1963. Since the data compilations available were completely inadequate for the task at hand, the tedious program of compiling and plotting was undertaken. As the work progressed an attempt was made to eliminate many of the obvious errors and inconsistencies found in the literature and existing compilations.
Date: February 1965
Creator: Stewart, Leona
Partner: UNT Libraries Government Documents Department
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Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.3 Chromel-Alumel Thermocouples

Description: This report is a segment providing smoothed thermocouple tables of extended significance in degrees Celsius (°C) for [section name]. It includes [1] a figure illustrating the difference in microvolts between the values in the smoothed table and those in the reference table and [2] a reference table containing (i) a tabulation of smoothed emf (in absolute millivolts) vs. temperature for a specific thermocouple and (ii) a tabulation of emf differences.
Date: March 1965
Creator: Adams, R. K. & Davisson, E. G.
Partner: UNT Libraries Government Documents Department
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Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.12 Alumel-Chromel Cryogenic Thermocouple

Description: This report is a segment providing smoothed thermocouple tables of extended significance in degrees Celsius (°C) for [section name]. It includes [1] a figure illustrating the difference in microvolts between the values in the smoothed table and those in the reference table and [2] a reference table containing (i) a tabulation of smoothed emf (in absolute millivolts) vs. temperature for a specific thermocouple and (ii) a tabulation of emf differences.
Date: March 1965
Creator: Adams, R. K. & Davisson, E. G.
Partner: UNT Libraries Government Documents Department
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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
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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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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
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STEP Project Quarterly Technical Report: January-June 1964

Description: Report regarding the Safety Test Engineering Program (STEP), the transient and destructive testing of the aerospace SNAP 10A/2 reactor, and the evaluation of the results of these tests.
Date: June 1965
Creator: U.S. Atomic Energy Commission. Idaho Operations Office.
Partner: UNT Libraries Government Documents Department
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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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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
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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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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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SNAPTRAN 2/10A-3 destructive test results

Description: Report regarding a rapid water immersion test on a SNAP 10A/2 reactor core. It includes the radiological results of the tests and the reactor behavior that influenced these results.
Date: 1965
Creator: Brockett, George F.; Fletcher, R. D. (Robert Dearborn), 1917-; Dinneen, G. A.; Cordes, O. L. & Kessler, W. E.
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
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