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448
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437
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239
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57
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245
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RADIATION CREEP
Several theories of metal creep and radiation damage are studied, in order to determine whether creep rates under various conditions of irradiation can be predicted theoretically. It is found that if the creep is of the recovery type, and if the diffusion coefficient for radiationinduced vacancies is large enough, creep rates may be increased within a limited temperature range. Otherwise, radiation has no effect on creep rates. (T.F.H.)
Date:
December 1, 1957
Creator:
Gregory, D.P.
System:
The UNT Digital Library
Atmospheric Signals From Explosions and Their Interpretation
Results are reported from a series of experimental highexplosive shots under inversion conditions at the Nevada Test Site which were made in an attempt to refine blast prediction techniques. Applications of the data in determinations of the amount of energy which remains in the blast wave as it reaches acoustic level and in determinations of the magnitude of the reflection factor when the blast wave strikes the ground are discussed. Data on shock wave propagation are presented graphically. It is concluded that the blast phenomenology of high-altitude shots can be predicted by using modified Sach's scaling. With some extrapolation to the height-of-burst versus blast-yield curve, it should be possible to make order-of-magnitude predictions of blast effects from high-altitude shots up to heights of burst of 1,000,000 ft. (C.H.)
Date:
December 1, 1959
Creator:
Reed, J. W.
System:
The UNT Digital Library
Sodium Graphite Reactor. Quarterly Progress Report, July-September 1954
Technology of the Sodium Graphite Reactor. Reactivity calculations were made to study the application of steadystate plutonium feedback techniques to the use of diffusion plant tails for reactor fuel feed material. The performance and design of a twin core SGR power plant are given. Thermal neutron flux distribution measurements are reported for a six-rod fuel cluster and for a hollow uranium rod. A power cost calculation was made for a 1000-Mw SGR Th-U/sup 233/ breeder reactor which starts up on Th--U/sup 235/ alloy. Calculations were made on neutron leakage through the SRE shield. Research on reactor fuel elements and reactor materials are described. Corrosion and irradiation damage data at 5 x 10/sup 7/ r dose (150 deg F) on toluene as the SRE shield coolant indicate that the radioinduced corrosion of Fe, Al, and Cu in the SRE shield should be negligible. Preliminary results are summarized for l-Mev electron ir radiation studies of terphenyls at 400 to 450 deg C. Sodium Reactor Experiment. Progress is reported for various portions of the SRE project: reactor design and evaluation, fuel elements, moderator, reflector, structure, reactor cooling and heat transfer, instrumentation and control, shielding, and reactor services. (D.L.C.)
Date:
December 1, 1954
Creator:
Siegel, S. & Inman, G.M. eds.
System:
The UNT Digital Library
DISCUSSION OF PERFORMANCE CALCULATIONS OF NUCLEAR ROCKET ENGINES
BS>Some of the fundamental relationships in a nuclear rocket engine are discussed. The equations required to calculate the performance of the rocket are presented. The problems associated with these calculations are also pointed out. (auth)
Date:
December 21, 1959
Creator:
Semple, E.L.
System:
The UNT Digital Library
Report of the Forty-Fourth National Conference on Weights and Measures, 1959
Report of the annual conference on weights and measures, hosted by the U.S. National Bureau of Standards in Washington D.C. It includes conference proceedings, a list of attendees, information about committees and officers, and other reports or commentaries discussed at the meetings.
Date:
December 18, 1959
Creator:
United States. National Bureau of Standards.
System:
The UNT Digital Library
Investigation of the Aerodynamic Characteristics of the NACA RM-10 Missile (With Fins) at a Mach Number of 1.62 in the Langley 9-Inch Supersonic Tunnel
Report presenting an investigation of a fin-stabilized scale model of the NACA RM-10 missile at a Mach number of 1.62. Measurements were made of the lift, drag, and pitching moment of the finned body over a range of angles of attack. Comparisons with the results from other testing facilities are also provided.
Date:
December 19, 1952
Creator:
Coletti, Donald E.
System:
The UNT Digital Library
Petroleum Engineering Study of the Weber Pool, Washington County, Oklahoma
Report issued by the U.S. Bureau of Mines on the development and exploitation of oil from Weber Pool in Washington County. Studies on possible recovery of known oil reserves are presented. This report includes maps, illustrations, tables, and graphs.
Date:
December 1950
Creator:
Johnston, Kenneth H. & Moot, C. W., Jr.
System:
The UNT Digital Library
Estimate of Known Recoverable Reserves of Coking Coal in Indiana County, Pennsylvania
Report issued by the U.S. Bureau of Mines on the known deposits of coking coal in Indiana County. The properties and characteristics of the coal and coal blends sampled are presented. The report includes tables and maps.
Date:
December 1950
Creator:
Dowd, James J.; Turnbull, Louis A.; Toenges, Albert L.; Cooper, H. M.; Abernethy, R. F.; Reynolds, D. A. et al.
System:
The UNT Digital Library
National Motor-Gasoline Survey: Summer 1950
Report issued by the U.S. Bureau of Mines on the motor fuels sold in the U. S. during the summer of 1950. Properties and trend characteristics of the fuel samples collected are presented. This report includes tables, graphs, and a map.
Date:
December 1950
Creator:
Blade, O. C.
System:
The UNT Digital Library
Estimate of Known Recoverable Reserves and the Preparation and Carbonizing Properties of Coking Coal in Anderson County, Tennessee
Report issued by the Bureau of Mines over investigations of coking coal reserves of Anderson County, Tennessee. Testing to determine suitability for producing metallurgical coke is also presented. This report includes tables, maps, photographs, and illustrations.
Date:
December 1955
Creator:
Williams, Lloyd; James, Curtis; Gandrud, B. W. & Reynolds, D. A.
System:
The UNT Digital Library
Model 1C shield design
None
Date:
December 22, 1958
Creator:
Henry, A. H.
System:
The UNT Digital Library
NUCLEAR PROPERTIES OF ANTINUCLEONS
None
Date:
December 10, 1959
Creator:
Segre, Emilio
System:
The UNT Digital Library
An evaluation of the Weldon Spring Feed Preparation and Sampling Plant
A description of the new Weldon Spring Feed Preparation and Sampling Plant for uranium concentrates is given. Prior to the startup of this plant the auger to be later installed was used in an evaluation program to test reliability for representative sampling and uniformity both within drums and between drums of various concentrates. Results of this program were used as a reference for the sampling plant evaluation which involved successive auger and mechanical sampling of a series of lots of several concentrates, followed by moisture determinations, uranium assays, and statistical analyses of the data. From the final results conclusions are drawn concerning the suitability of the mechanical sampling system for the concentrates examined.
Date:
December 1, 1958
Creator:
Ziegler, W. A.; Swaney, D. R.; Huston, S. H.; Todd, J. E. & Kuehn, M. N.
System:
The UNT Digital Library
The Preparation of Beta Silicon Carbide
This report explores the production of beta silicon carbide, a low-temperature, cubic modification of cubic silicon carbide. The temperature, heating time, type of starting material, and proportion of starting materials were all varied in order to test yields of beta silicon carbide.
Date:
December 29, 1952
Creator:
Gambino, J. R.; Mixer, W. G., Jr.; Wagner, H. E. & Harman, Cameron G.
System:
The UNT Digital Library
Evaluation of Oxidation-Resistant Ceramics for High-Temperature Reactor Elements
Abstract: "As a possible aid in the selection of ceramic materials for use in the fabrication of high-temperature reactor elements, the reported properties of 23 refractory oxidation-resistance ceramic compounds are tabulated. The thermal stresses and heat throughout capacities for nine of these compounds are estimated for conditions of steady heat flow and uniform heat generation in the temperature range of 1500 to 2500 F. The compounds studied have macroscopic thermal-neutron-absorption cross sections lower than 0.2 per centimeter. Data concerning the high-temperature stability of uranium compounds are tabulated for those with melting points above 2450 F."
Date:
December 1, 1952
Creator:
Harman, Cameron G.; Ferrell, Edward Francis.; Wagner, H. E. & Quirk, J. F.
System:
The UNT Digital Library
Mechanical Properties of Zirconium-Tin Alloys
Abstract: "The mechanical properties and corrosion resistance of induction-melted, zirconium-tin alloys have been determined. The alloys investigated contained from zero to five per cent tin and up to 0.3% carbon. The zirconium used was United States Bureau of Mines sponge zirconium. The mechanical properties investigated include the tensile, hot-hardness, and impact properties."
Date:
December 22, 1952
Creator:
Schwope, A. D. & Chubb, Walston
System:
The UNT Digital Library
The Rolling of Uranium
The following report discusses the method of rolling uranium rods and strips under various rolling conditions and the roll-separating force measured.
Date:
December 30, 1952
Creator:
Saller, Henry A.; Keeler, J. R. & Donley, R. J.
System:
The UNT Digital Library
Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Tenth Letter Report, October 1 to December 1, 1959
Introduction: "This is the tenth letter report on ARF Project C 127, entitled "Preliminary Studies of Scavenging Systems Related to Radioactive Fallout." This report covers the period from October 1 to December 1, 1959."
Date:
December 18, 1959
Creator:
Stockham, John D. & Rosinski, John
System:
The UNT Digital Library
Topical Report on Refining of MgX and Other Uranium-Bearing Materials
This report discusses a study which explores the effects of feed and acidity on extractive methods. From abstract: "Results from fractional precipitation of MgX from dilute sulfuric acid solutions indicate that, in the presence of sufficienct iron, phosphate is precipitated as ferric phosphate, and not as uranyl phosphate."
Date:
December 31, 1950
Creator:
Ewing, R. A.; Belcher, R. L.; Kiehl, S. J., Jr. & Bearse, A. E.
System:
The UNT Digital Library
The Rolling of Thorium Rod
Report discussing the rolling of thorium rods. Abstract: "Thorium rods, 1-7/16 inch in diameter, were rolled from Ames castings. The billets were roughed down in diamond-grooved rolls and finished in hand-rounding rolls. Remelted chips as well as primary-metal castings were rolled, and both yielded satisfactory rods. The surface quality of the rods was generally excellent, and the machined slugs were free of seams."
Date:
December 19, 1951
Creator:
Saller, Henry A.; Keeler, J. R. & Donley, R. J.
System:
The UNT Digital Library
A Study of Thorium-Base Alloys
Report discussing studies testing various thorium alloys consisting of either Ames thorium and up to 5% of various additions or Ames thorium and up to 50% uranium. Effects of molybdenum additions for fusion welding, and cold-work strengthening were also tested. Methods, experimental data, and discussion is included.
Date:
December 26, 1951
Creator:
Goldhoff, R. M.; Ogden, Horace R. & Jaffee, Robert Isaac, 1917-
System:
The UNT Digital Library
Progress Report on the Concentration of Pitchblende
Abstract: "The results of leaching studies on sulphide froth products obtained from the flotation of high-sulphur pitchblende are presented. The distribution of molybdenum in flotation products is also given. The flotation test at Middlesex is evaluated."
Date:
December 31, 1950
Creator:
Wesner, A. L.; Tangel, O. F. & Richardson, A. C.
System:
The UNT Digital Library
Los Alamos Power Reactor Experiment and its Associated Hazards
The following report describes the high pressure and temperature homogeneous reactor experiment which has been started at Los Alamos, as well as the hazards and safety aspects for the experiments.
Date:
December 2, 1953
Creator:
King, L. D. P.
System:
The UNT Digital Library
The Reaction of Uranium With Purified Water
Report discussing the reaction of uranium with pure water. The reaction was followed by using a method of measuring hydrogen evolution.
Date:
December 1951
Creator:
Waber, S. F. & Waber, James T.
System:
The UNT Digital Library