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Activation of electrical machinery. Supplement 1. [Preliminary evaluation; not applicable to ground tests]

Description: The following analysis of the induced radioactivity in SNAP-50/SPUR electrical machinery having a high cobalt content is submitted. Induced radioactivity in the flight vehicle will contribute negligibly to allowable radiation levels. This is especially so due to the low neutron to gamma ratio of assumed radiation damage tolerances to semiconductors. A calculation to estimate the order of magnitude of induced radioactivity in cobalt is attached. The calculation is based on a best guess of the ne… more
Date: November 15, 1963
Creator: Smolen, J.R.
Partner: UNT Libraries Government Documents Department
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Beta Radiation Processing at Rigorous Conditions

Description: Introduction: The literature reflects ever expansive studies of radiation chemistry over the past twenty years However, in the application of radiation processing to chemical reactions, in general and excepting a few isolated cases, the yield of useful products have been so low as to preclude practical utilization. Thus, for many reactions,radiation alone at ambient conditions is not a sufficient agent for economical production. Hence, we are led to the investigation of radiation effects on … more
Date: November 15, 1963
Creator: Yavorsky, P. M. & Gorin, E.
Partner: UNT Libraries Government Documents Department
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Control Drum Actuator Checker

Description: The Control Drum Actuator Checker is used to verify the operation of the hydraulic control drum actuators before they are installed on the reactor. It provides for local checkout after installation. It provides for local checkout after installation. It also provides for pre-installation hydraulic leak and pneumatic seal test on individual actuator assemblies.
Date: November 15, 1963
Partner: UNT Libraries Government Documents Department
open access

Development of salt velocity technique

Description: The salt velocity technique for measuring coolant flow through a SNAP 8 tri-cusp channel was studied and developed. The parameters important in obtaining reproducible data were investigated and a test procedure, which yields dath of good precision, was developed. Dath were taken on a tri-cusp channel with flush circular electrodes (0.125 inch O.D.) as well as on a tri-cusp channel with parallel plate electrodes (0.006 inches thick, 0.250 inches long), which were situated 0.050 inches apart and … more
Date: November 15, 1963
Creator: Daleas, R. S.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories monthly activities report, October 1963

Description: This is the monthly report for the Hanford Laboratories Operation, October 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: November 15, 1963
Partner: UNT Libraries Government Documents Department
open access

Irradiation Processing Department Monthly Report: October 1963

Description: This document details activities of the irradiation processing department during the month of October, 1963. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; and Financial Operation.
Date: November 15, 1963
Creator: Hanford Atomic Products Operation. Irradiation Processing Department.
Partner: UNT Libraries Government Documents Department
open access

Nuclear Superheat Quarterly Project Report: Seventeenth Quarter, August-October 1963

Description: From introduction: "This is the seventeenth in a series of quarterly reports which cover the progress and results from the conceptual designs, economic evaluations and research and development work performed by the General Electric Company as part of Contract AT(01-3)-189, Project Agreement No. 13."
Date: November 15, 1963
Creator: Flock, W. L.
Partner: UNT Libraries Government Documents Department
open access

REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, OCTOBER 1963

Description: Research and development progress is reported on BORAX-V, fast-reactor physics, fast-reactor fuel, EBRII, FARET, applied nuclear physics, theoretical nuclear physics, reactor fuels, reactor materials, metallurgy alpha - gamma hot cell, heat engineering research, chemical separations, plutonium recycle program, magnetohydrodynamics, rocket fuel test reactor, nuclear safety, and TREAT. (M.C.G.)
Date: November 15, 1963
Partner: UNT Libraries Government Documents Department
open access

SRE Systems and Components Experience. Core II

Description: The design and performance of SRE Core II fuel elements, moderator cans, hot traps, cold traps, control elements, pumps, main primary heat exchanger, valves and sodium piping, and instrumentation are discussed. (R.E.U.)
Date: November 15, 1963
Creator: Pearson, E. N.
Partner: UNT Libraries Government Documents Department
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Summary report, Flexible VSR`s and VSR channel sleeve development programs

Description: (VSR = vertical safety rod.) This report summarizes results of development programs which have evaluated vertical rod channel sleeving materials and provided flexible vertical rods, acceptable for both interim use before rod channel sleeving, and for subsequent use in sleeved channels. B{sub 4}C is the rod material; graphite and Al oxide are among the sleeve materials.
Date: November 15, 1963
Creator: Kempf, F. J.
Partner: UNT Libraries Government Documents Department
open access

A Uranium Dioxide Fuel Rod Center Melting Test in the Vallecitos Boiling Water Reactor

Description: Technical report describing that as part of the AEC Fuel Cycle Program, tests are being conducted to evaluate the significance of current fuel design limitations that do not permit the maximum fuel temperature to exceed the melting point of UO2. The reliability of prediction of the fuel rod operating conditions that will cause melting of the UO2 was evaluated by means of a calibration test conducted in the Vallecitos Boiling Water Reactor. Conclusions: (a) The central portion of the 3.15-cm dia… more
Date: November 15, 1963
Creator: Williamson, H. E. & Hoffmann, J. P.
Partner: UNT Libraries Government Documents Department
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