Resource Type
Collection
Serial/Series Title
NACA Research Memorandums
27
Atomic Energy Commission Reports
6
AECU (Series)
2
NACA Technical Reports
2
U.S. Atomic Energy Commission Idaho Operations Office Reports
2
Atomic Power Development Associates Reports
1
Hanford Works Reports
1
ORNL (Series)
1
Oak Ridge National Laboratory Reports
1
Report (U.S. Atomic Energy Commission)
1
3 More
Country
58 Matching Results
Results open in a new window/tab.
Results:
1 - 24 of
58
next
A Study of Location Times for Positions Arranged on a Panel in a Random and an Ordered Manner
The results of an experimental pilot study on the location time, for a sequence of N specified positions on a panel, are given for 1 <_ N <_ 30. The positions to be located were randomly arranged on one set of panels and arranged according to an ordering scheme on a second set of panels. Th location time for N positions randomly arranged on a panel varies approximately as N(2). In the case of an order arrangement the location time is essentially proportional to N. Even for as few as 30 positions, the location time for an random arrangement was twelve times greater than for an order panel. For 60 positions the ratio would be 19, and for 90 positions the ratio would be 26.
Date:
May 25, 1955
Creator:
Beeler, J. R.
System:
The UNT Digital Library
Studies on the Experimental Pathology and Biochemistry of the Pulmonary Granulomatosis of Beryllium Workers. Section II, Consolidated Progress Report. Supplement: a Review of the Physical Chemistry of Beryllium
The status of research is reviewed in a study of pulmonary granulomatosis in beryllium workers. Equipment for use in dust exposure studies is described. Preliminary results are reported from studies on the tissue distribution and pathological effects of beryllium dust in rats; the physical chemistry of solutions of beryllium salts; the effects of beryllium on enzyme systems, and the effects of ascorbic acid on beryllium excretion.
Date:
April 25, 1955
Creator:
Schepers, G. W. H. (Gerrit Willem Hendrik), 1914-
System:
The UNT Digital Library
Preliminary Results of APPR Critical Experiments, Part I.
This memorandum is the first in a series reporting progress in the program of critical experiments in the ORNLArmy Package Power Reactor Project. The critical assembly, designated as CA-25, is analogous to the APPR design core and consists of 45 fuel boxes, in a 7 x 7 array with the corners removed, contaIned in a large water tank. Two sides of each box are slotted for the insertion and positioning of any desired loading of eighteen plates of fuel, structural material, and poison. The array is submerged in water to provide a moderated and reflector. Enriched uranium metal, in two-mil-thick foils 2.5 x 22 in, is encased in type 304 stainless steel sheets, 2.7 x 23 x 0.0105 in., to form fuel plates. Stainless steel plates, 2.7 x 23 x 0.025 in. are used to simulate additional steel in the APPR core. It is, therefore, possible to maintain an essentially constant metal to water ration in the assembly when the fuel content is varied. The fuel is distributed as uniformly as possible in all boxes and a symmetrical distribution of materials is maintained in the core at all times. Fuel plates containing half-width (1.25 in) uranium foils are provided for …
Date:
November 25, 1955
Creator:
Williams, D. V. P.
System:
The UNT Digital Library
Atmospheric Contamination Associated with Inert-Gas-Shielded, Consumable Electrode Welding
Apparent excessive concentrations of atmospheric contamination which were reported to be associated with an inert-gas-shielded consumable electrode arc wielding operation were studied to evaluate the potential health hazards. A study was made of the concentrations of metal fume and gaseous products of the operation as well as the spectrum of ultraviolet radiation. Recommendations for necessary controls were made.
Date:
July 25, 1955
Creator:
Adley, F. E. & Gill, W. E.
System:
The UNT Digital Library
Trip report: Battelle Memorial Institute, March 22-23, 1955
Nickel-plated uranium corrosion samples, 1 inch dia. X 0.180 inch thick, press-clad with 30-mil aluminum at both 10 and 15 thousand psi, show improved corrosion resistance over samples press-clad at 6 thousand psi with the same time-temperature conditions. Design of equipment for the internal cladding of uranium tubes is progressing. The basic tools will be applicable to several variations of the proposed method of {open_quotes}inverse die sinking.{close_quotes} Analyses of double and triple melted Horizons` electrolytic thorium show a significant increase of H{sub 2} and O{sub 2}, upon remelting with a corresponding increase in the hardness of the metal.
Date:
March 25, 1955
Creator:
O`Leary, W. J. & Herries, R. R.
System:
The UNT Digital Library
Laboratory project for isolation of plutonium
Construction of proposed facilities to be operated under Technical Division supervision for research with plutonium is discussed. An attempt is made in this memorandum to visualize the research program for such a facility for the next five years, to aid in determining whether the cost of providing such facilities is justified.
Date:
July 25, 1955
Creator:
Jenkins, W. A.
System:
The UNT Digital Library
Contaminated Equipment Renovation Shop. A Preliminary Study
The intent of this study is to establish more completely the justifications for constructing a decontamination plant as outlined in Budget Item B 5720, ``Containmented Equipment Renovation Shop,`` FY 1957, Plant and Equipment Projects. In particular, the economic incentives have been explored. The question or idea has been investigated of assigning a dollar value to engineering information which might be obtained from examining contaminated equipment which has failed from unknown causes. Heretofore it has not been possible to examine such equipment because suitable decontamination facilities have not been available. An effort has been made to uncover all possible uses for the proposed facility in order that the estimated capital and operating costs might be evaluated in terms of all the functions which the proposed plant might perform.
Date:
August 25, 1955
Creator:
Hughes, H. R.
System:
The UNT Digital Library
Steam loss at 190-B, D, DR, F, and H Buildings
None
Date:
February 25, 1955
Creator:
Stainken, F. A. R.
System:
The UNT Digital Library
Hanford Atomic Products Operation monthly report, December 1954
This document presents a summary of work and progress at the Hanford Engineer Works for December 1954. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summarizes work for the Technical, Design, and Project Sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities and General Services, Employee and Public Relations, and Community Real Estate and Services departments have sections presenting their monthly statistics, work, progress, and summaries.
Date:
January 25, 1955
Creator:
unknown
System:
The UNT Digital Library
Nuclear metallurgy lectures. Chapter 12, Effect of irradiation on the properties of fissionable and non-fissionable materials
This report summarizes the effect of irradiation on the properties of fissionable and non-fissionable materials. General property changes, irradiation of zirconium, zirconium-tin alloys, the irradiation of aluminium, irradiation of thorium and uranium, are a few of the topics discussed.
Date:
May 25, 1955
Creator:
Hueschen, R. E.
System:
The UNT Digital Library
Trajectory-Wise Analysis of Immobilized Plasma Including Electrons. Machine Calculations
Abstract: "The trajectory analysis of an immobilized plasma has been generalized to include the presence of electrons having a far similar radius of gyration and, therefore, fitting readily into the broader scale structure established by the ions. This problem has been adapted to machine calculations and the results for various strengths plasmas have been calculated."
Date:
March 25, 1955
Creator:
Tonks, Lewi, 1897-1971 & Keirstead, Ralph
System:
The UNT Digital Library
Development of the Higgins Continuous Ion Exchange Contactor for the Recovery of Uranium from Leached Ore Pulps
From introduction: "The objective of this report is to present the results and describe the tests of both the 2-in. D and 6-in. D contractors using mill pulp feeds. Work on determining resign attrition is also reported. ORNL-CF-52-12-101 described the results of preliminary tests using synthetic ore pulps."
Date:
March 25, 1955
Creator:
Higgins, I. R.; Hancher, C. W. & Arehart, T. A.
System:
The UNT Digital Library
MEDICAL AND HEALTH PHYSICS QUARTERLY REPORT FOR JANUARY, FEBRUARY, MARCH 1955
None
Date:
April 25, 1955
Creator:
unknown
System:
The UNT Digital Library
RESEARCH AND DEVELOPMENT IN THE FIELD OF THORIUM CHEMISTRY AND METALLURGY. Monthly Progress Report for April 16 to May 15, 1955
A continuous belt drier capable of handling 1000 lbs of oxycarbonate per day was completed, installed, and operated to produce a satisfactory product for chlorination. An experimental chlorinator was also completed. All necessary pants were completed for the fabrication of Horizons' Mark VI continuous electrolytic cell. Evaluations of oxycarbonate materials for chlorination wiih varying chlorinating agents were made, and many of the variables such as water content and CO/sub 2/ values were established. Extremely ductile rods were obtained from the direct extrusion of Th metal powder. Plans were completed for the Mark VI electrolytic cell. Work was continued toward the development of a semi-continuous operating electrolytic cell of 7500-a rated capacity. (D.E.B.)
Date:
May 25, 1955
Creator:
Wyatt, J.L.
System:
The UNT Digital Library
A THEORY FOR THE DESIGN OF DISSOLVER FOR SLUG-TYPE REACTOR FUELS
None
Date:
January 25, 1955
Creator:
Jury, S.H.
System:
The UNT Digital Library
Development and Properties of Uranium-Base Alloys Corrosion Resistant in High Temperature Water. Part 1. Alloys Without Protective Cladding
None
Date:
April 25, 1955
Creator:
Bostrom, W. A.; Burkart, M. W.; Halteman, E. K.; Leggett, R. D.; McGeary, R. K. & Padden, T. R.
System:
The UNT Digital Library
RESUME' OF URANIUM ALLOY DATA-VIII
None
Date:
February 25, 1955
Creator:
Lustman, B.
System:
The UNT Digital Library
HIGH TEMPERATURE STRAIN GAGE RESEARCH. Summary Report
None
Date:
January 25, 1955
Creator:
Tatnall, F.G.
System:
The UNT Digital Library
QUARTERLY SUMMARY RESEARCH REPORT IN ENGINEERING FOR JANUARY, FEBRUARY, MARCH 1955
None
Date:
June 25, 1955
Creator:
unknown
System:
The UNT Digital Library
HRT PROCESS FLOWSHEETS. Revision 1
None
Date:
August 25, 1955
Creator:
Zapp, F. C.
System:
The UNT Digital Library
A STUDY OF LOCATION TIMES FOR POSITIONS ARRANGED ON A PANAL IN A RANDOM AND AN ORDERED MANNER
None
Date:
May 25, 1955
Creator:
Beeler, J.R.
System:
The UNT Digital Library
STABILITY OF HOMOGENEOUS REACTORS
None
Date:
May 25, 1955
Creator:
Kasten, P. R.
System:
The UNT Digital Library
Shock Hydrodynamics of an Exploding Steam Pressure Vessel. Final Report
The purpose of these investigations is to determine, grossly and simply, if a shock hazard exists from an explosive failure of the pressurizer vessel within the vapor container. Because of the geographical location of the reactor, an explosive failure which ruptured the vapor container might release radioactive contamination from the reactor to nearby inhabited communities. The study is considered more as a generic problem than of a specific design and is concerned with the shock hydrodynamics of an exploding steam vessel. (auth)
Date:
November 25, 1955
Creator:
Lype, E. F. & Porzel, F. B.
System:
The UNT Digital Library
Effects of Elevated Temperatures on the Properties of Portland Cement Mixtures Related to Surface Removal and Decontamination
From abstract: The effect of heat on the surface removal of concrete was studied by conducting brush tests on samples which had been subjected to prolonged high temperatures in an oven or in direct contact with an oxy-propane flame. Other methods of heat-treating surface layers of concrete were investigated by direct application of an oxy-aluminum torch on the surface and by the exothermic chemical reactions of pyrotechnic compositions placed directly on the surface.
Date:
August 25, 1955
Creator:
Heiskell, R. H.; Black, R. H.; Crew, R. J. & Lee, H.
System:
The UNT Digital Library