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Storm Data and Unusual Weather Phenomena, Volume 2, Number 10, October 1960

Description: Monthly report containing a chronological listing, by state, of hurricanes, tornadoes, thunderstorms, hail, floods, drought conditions, lightning, high winds, snow, temperature extremes and other weather phenomena. It also provides information on storm paths, deaths, injuries, and property damage.
Date: January 30, 1960
Creator: United States. Weather Bureau.
Partner: UNT Libraries Government Documents Department
open access

PCTR Measurements of the EGCR Lattice Parameters

Description: Measurements of k∞, f, p, and ∈ have been performed in the PCTR in support of the EGCR Program. The values listed below were obtained for the 21.875-inch cell used in the PCTR measurements. They are for a nonabsorbing (helium or vacuum) atmosphere.
Date: March 30, 1960
Creator: Nichols, P. F.; Engesser, F. C. & Oakes, T. J.
Partner: UNT Libraries Government Documents Department
open access

Polfit, A 704 Program For Polynomial Least Squares Fitting

Description: A polynomial least squares fitting subroutine has been written for the IBM-704 computer. This subroutine may be used in any Fortran II program where a least squares fit is desired. A calling program has been written to do a polynomial least squares fit, error analysis, and give solutions of the resulting equations for any desired values of the independent variable.
Date: March 30, 1960
Creator: Lietzke, M. H. & Lietzke, Marjorie P.
Partner: UNT Libraries Government Documents Department
open access

REDUCTION OF CUPRIC OXIDE BY HYDROGEN. I. FUNDAMENTAL KINETICS

Description: Basic studies of the kinetics of the reduction of copper oxide were made to establish the effect of the solid phase on the over-all reaction kinetics The reaction CuO + H/sub 2/ at the only rea Cu + H/sub 2/O consisted of an induction stage, an acceleration or autocatalytic stage terminating at about 35% reduction of the exide, and a decreasing-rate stage The reduction rates for each stage were dependent on the nature of the initial oxide, the degree of subdivision of the oxide, and the tempera… more
Date: March 30, 1960
Creator: Bond, W. D. & Clark, W. E.
Partner: UNT Libraries Government Documents Department
open access

SM-2 REACTOR CORE AND VESSEL REVIEW REPORT FOR PERIOD DECEMBER 15, 1959 TO MARCH 18, 1960

Description: The SM-2 core lifetime was calculated and stuck rod criteria formulated. The control system could shutdown the core under the most adverse conditions with any single rod stuck out. The one-half-inch Eu/sub 2/O/sub 3/ flux supressors adequately supressed the power spike at the bottom of the core. The nuclear effects of increasing the dimensione of the fuel matrix were calculated. A new analysis of various reactivity measuremerts performed durirg the SM-2 critical experiments was made to test the… more
Date: March 30, 1960
Creator: Hoover, H.L.
Partner: UNT Libraries Government Documents Department
open access

Storm Data and Unusual Weather Phenomena, Volume 2, Number 2, February 1960

Description: Monthly report containing a chronological listing, by state, of hurricanes, tornadoes, thunderstorms, hail, floods, drought conditions, lightning, high winds, snow, temperature extremes and other weather phenomena. It also provides information on storm paths, deaths, injuries, and property damage.
Date: March 30, 1960
Creator: United States. Weather Bureau.
Partner: UNT Libraries Government Documents Department
open access

The Trumpeter Swan: its History, Habits, and Population in the United States

Description: Summary of the trumpeter swan, including geographic distribution, habitats for breeding and wintering, life cycle, nesting, food, limiting factors, longevity, population dynamics, and human management.
Date: April 30, 1960
Creator: Banko, Winston E.
Partner: UNT Libraries Government Documents Department
open access

Application of Nuclear Power Supplies to Space Systems

Description: Studies were made to ascertain what useful satellite and/ or space missions may be accomplished with the SNAP 2, 8, and 10 power systems within the 1960 to 1970 time period, to delineate useful satellite and/or space missions which would most profitably employ nuclear power sources, to ascertain what restrictions are imposed on various payloads as a result of having a nuclear power system on board, and to investigate the general vehicle integration and installation requirements of the SNAP 2 an… more
Date: June 30, 1960
Partner: UNT Libraries Government Documents Department
open access

Boiling Songs and Associated Mechanical Vibrations

Description: From introduction: The study is based entirely on observations which have been made at a number of different installations at which boiling songs and vibrations were noted during heat transfer experiments.
Date: June 30, 1960
Creator: Firstenberg, H.
Partner: UNT Libraries Government Documents Department
open access

Corrosion Studies for a Fused Salt-Liquid Metal Extraction Process for the Liquid Metal Fuel Reactor

Description: Corrosion screening tests were carried out on potential materials of construction for use in a fused salt-liquid metal extraction process plant. The corrodents of interest were NaCl--KCl-- MgCl/sub 2/ eutectic, LiCl--KCl eutectic, Bi-- U fuel, and BiCl/sub 3/, either separately or in various combinations. Screening tests to determine the resistance of a wide range of commercial alloys to the corrodents were performed in static and tilting-furnace capsules. Some ceramic materials were tested in … more
Date: June 30, 1960
Creator: Susskind, H.; Hill, F. B.; Green, L.; Kalish, S.; Kukacka, L. E.; McNulty, W. E. et al.
Partner: UNT Libraries Government Documents Department
open access

Depassivation of 304-L Stainless Steel in Sulfex Decladding Solutions

Description: In the Sulfex process, stainless steel cladding, generally 304-L, is removed from fuel elements by dissolution in boiling four to six molar sulfuric acid. When cladding removal is complete, the decladding solution is removed is removed to waste. The exposed fuel cores are rinsed and dissolved in nitric acid.
Date: June 30, 1960
Creator: Duke, E. M.
Partner: UNT Libraries Government Documents Department
open access

Final Safety Analysis Report: SNAP 1A Radioisotope Fueled Themonuclear Generator

Description: The following report is the final safety analysis report for the Task 2 Radioisotope Powered Thermoelectric Generator prepared by The Martin Company. It presents analyses, tests and evaluation of the operational safety criteria for the generator.
Date: June 30, 1960
Creator: Dix, George P.
Partner: UNT Libraries Government Documents Department
open access

Final Safety Analysis Report--SNAP 1A Radioisotope Fueled Thermoelectric Generator

Description: The safety aspects involved in utilizing the Task 2 radioisotope-powered thermoelectric generator in a terrestrial satellite are described. It is based upon a generalized satellite mission having a 600-day orbital lifetime. A description of the basic design of the generator is presented in order to establish the analytical model. This includes the generator design, radiocerium fuel properties, and the fuel core. The transport of the generator to the launch site is examined, including the shippi… more
Date: June 30, 1960
Creator: Dix, G. P.
Partner: UNT Libraries Government Documents Department
open access

FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. A Topical Report on SUB-SURFACE COATINGS FOR FUELED GRAPHITE SPHERES

Description: An exploratory program on subsurface coatin8s for graphite fuel elements is summarized. A number of coatings with various melting points which could be located beneath the surface of a fueled graphite sphere were investigated. Of the materials with lower melting points. nickel and a special glass compound appeared to form continuous coatings when a hot-pressing technique was employed. Several materials with high melting points. such as Ti, Cr, and MoSi/sub 2/, showed some promise, even though p… more
Date: June 30, 1960
Partner: UNT Libraries Government Documents Department
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NS Savannah Nuclear Merchant Ship Design Review. Summary Report

Description: Results of a survey covering the safety, adequacy, and reliability of certain design and construction features pertaining to the NS Savannah nuclear power plant and related systems are presented. (auth)
Date: June 30, 1960
Partner: UNT Libraries Government Documents Department
open access

OMR (Piqua) Unitized Control-Safety Rod Prototype Tests

Description: Abstract: A unitized magnetic jack driven control-safety rod has been developed for the 45.5 thermal megawatt organic moderated reactor (Piqua).
Date: June 30, 1960
Creator: Howell, J. D. & Weeks, C. C.
Partner: UNT Libraries Government Documents Department
open access

PERFORMANCE OF HNPF PROTOTYPE FREE-SURFACE SODIUM PUMP

Description: A free-surface centrifugal pump, incorporating a hydraulic bearing running in sodium, was operated at the conditions required for service in the Hallam Power Reactor. After difficulties arising from inadequate shaft clearances were alleviated, the pump performed properly at a flow rate of 7200 gpm of 945 gas-cooled F sodium at 150-ft head. Results Hallam plant. (auth)
Date: June 30, 1960
Creator: Atz, R. W.
Partner: UNT Libraries Government Documents Department
open access

Preliminary Report: 300 KWe Capsule Nuclear Power Plant Study

Description: This report describes progress made in the study of the feasibility of the concept, plant arrangement studies, and considerations pertaining to partial plant attendance. It is concluded that both the indirect and direct boiling cycles are feasible. The recommended reference design is the direct cycle, in a single capsule, with the turbine, generator and pumps on a single shaft.
Date: June 30, 1960
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
open access

Shielding of Pipes in the HFIR Primary Coolant System

Description: The thicknesses of ordinary concrete required to shield pipes in the ORNL High Flux Isotope Reactor primary water system were computed for normal operating conditions and for abnormal conditions such as a defective fuel plate or a meltdown of the fuel within the reactor. About 6 ft of concrete is required for the pipes at the outlet of the reactor, and 2 ft of concrete is required for the pipes located about 1 1/2 min downstream from the reactor vessel-. These thicknesses of concrete reduce the… more
Date: June 30, 1960
Creator: McLain, H A & Haack, L A
Partner: UNT Libraries Government Documents Department
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