Search Results

open access

ETR Nuclear Instrumentation : Final Report

Description: Report regarding the primary nuclear instrumentation at the Engineering Test Reactor (ETR) and early difficulties.
Date: February 3, 1960
Creator: Hanson, D. C.
Partner: UNT Libraries Government Documents Department
open access

Summary Report of Physics Measurements on SM-1 Core I

Description: Abstract: This technical report summarizes all core physics experiments performed on SM-1 Core I and SM-2 Rearranged and Spiked Core I throughout core life. These measurements were obtained on site during the 16.4 MWYR lifetime of SM-1 Core I and 1.6 MWYR lifetime of SM-1 Rearranged and Spiked Core I. SM-1 Core I was the first stainless steel - UO2 dispersion core to burn out in the Army Nuclear Power Program. Experimental techniques are described and a complete history of fuel movements in the core presented. Measurements include control rod bank positions during all core conditions, temperature and pressure coefficients, control rod calibrations, transient poison effects, source multiplication, and stuck rod positions. The effect of core rearrangement and spiking on core reactivity and core life is also reported. Applicable measurements from the SM-1 zero power experiments are included.
Date: February 6, 1962
Creator: Weiss, S. H.
Partner: UNT Libraries Government Documents Department
open access

Determination of Burnout Limits of Polyphenyl Coolants : Summary Report

Description: Report documenting an investigation undertaken "to establish the burnout limits of a polyphenyl mixture (...), diphenyl, Santowax R, and monoisopropyl-biphanyl for various pressures, fluid velocities, and fluid temperatures" (p. 7).
Date: February 14, 1958
Creator: Core, T. C. & Sato, K.
Partner: UNT Libraries Government Documents Department
open access

Heat Transfer in an Annulus with Asymmetric Heating

Description: Report concerning the "determination of the validity of using tube flow correlations for calculating pressure drop and heat transfer characteristics in thin annuli," the "validity of using Stein's heat flux asymmetry correction for parallel planes to calculate the heat transfer in asymmetrically heated thin annuli," and the "investigation of the effects of eccentricity on pressure drop, heat transfer, and temperature distribution in concentric ring fuel elements" (p. 5).
Date: February 1959
Creator: Lisin, Alexander Vladimir; Mackewicz, W. V. & Reynolds, William C., 1933-2004
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

The Elimination of Microwave Reflections

Description: Abstract: "The reflections of microwaves from the walls of a plasma-containing vessel are studied. The probable cause of the reflections is discussed, and several suggestions are made for eliminating the reflections from the waveguide in the vessel and particularly from the pyrex vessel wall and copper tubing surrounding the pyrex. Quarter-wave-thick carbon-filled plastics or glasses having a very low vapor pressure room most promising when placed inside the pyrex cylinder. BaTiO3 appears to be an excellent material when placed outside the vacuum."
Date: February 1, 1955
Creator: Beard, David
Partner: UNT Libraries Government Documents Department
open access

Organic Moderated Reactor Experiment : Safeguards Summary

Description: Abstract: This report presents a description of the Organic Moderated Reactor Experiment (OMRE), of the hazards associated with this experiment, and all of the safeguards taken to ensure the safety of the operating personnel and the population of the surrounding area.
Date: February 1, 1958
Creator: Sletten, H. L. & Blue, L. R.
Partner: UNT Libraries Government Documents Department
open access

Fluidization in Tapered Beds

Description: Abstract: The concept of a tapered fluidized bed is explored briefly. Data are given showing that in bench scale apparatus a tapered bed gives better fluidization with some materials that are difficult to fluidize in a conventional cylindrical bed.
Date: February 14, 1958
Creator: Rossmassler, W. R. & Harris, R. L.
Partner: UNT Libraries Government Documents Department
open access

Operation and Analysis of a 3000 KW Liquid Metal Model Steam Generator

Description: Abstract: A 3000 kw (thermal) bayonet duplex tube model steam generator was performance-tested in a liquid metal test loop at MSA Research Corporation, Callery, Pennsylvania, under the cognizance of Atomics International.
Date: February 28, 1961
Creator: Webster, L. J.
Partner: UNT Libraries Government Documents Department
open access

Design Modifications to the SRE during FY 1960

Description: Abstract: The means to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redesign of system components to utilize alternate coolants such as nitrogen, air, and NaK.
Date: February 15, 1961
Creator: Deegan, G. E.; Dermer, M. D.; Flanagan, J. S.; Gower, G. C.; Hall, R. J.; Hinze, R. B. et al.
Partner: UNT Libraries Government Documents Department
open access

Transistorized Trip Circuit for Critical Assemblies

Description: Abstract: A transistor trip circuit intended for critical assemblies and which provides maximum safety against human error or component failure is described.
Date: February 24, 1958
Creator: Wade, E. J. & Davidson, D. S.
Partner: UNT Libraries Government Documents Department
open access

The NAA 47 U - 10 Mo Fuel Irradiation Program for HNPF Core 1

Description: Abstract: Atomics International conducted a fuel irradiation program to investigate and define the behavior of U-10 Mo fuel at the temperatures and fission rates anticipated in Hallam Nuclear Power Facility (HNPF) Core I.
Date: February 1, 1965
Creator: Schmitt, A. R.; Willard, R. M. & Magnus, D. K.
Partner: UNT Libraries Government Documents Department
open access

Performance of Cesium Thermionic Diodes Operated in Series-Parallel Circuits

Description: Introduction: The purpose of this experiment is to determine the loss of electrical power output due to operating many unequally-heated cesium diodes, connected in series and parallel circuits.
Date: February 1, 1963
Creator: Holland, J. W.
Partner: UNT Libraries Government Documents Department
open access

Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968

Description: From Foreword: "Report containing information about ongoing research and development taking place in the Oak Ridge National Laboratory's Fuels and Materials Development Program. This includes a series of test reports covering such subjects as reactor fuels, the development of nitride fuels, and the effects of radiation on structural materials."
Date: February 1969
Creator: Oak Ridge National Laboratory. Metals and Ceramics Division.
Partner: UNT Libraries Government Documents Department
open access

Gas-Cooled Reactor Project Semiannual Progress Report: September 1964

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Gas-Cooled Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: February 1965
Creator: Trauger, D. B. & Whitman, G. D.
Partner: UNT Libraries Government Documents Department
open access

Neutron Physics Division Annual Progress Report, September 1, 1958

Description: Report containing a series of reports from members of the Oak Ridge National Laboratory's Neutron Physics Division.
Date: February 15, 1958
Creator: Oak Ridge National Laboratory. Neutron Physics Division.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen