The Identification and Determination of Trace Amounts of Rare Earth Elements in Graphite by Neutron Activation (open access)

The Identification and Determination of Trace Amounts of Rare Earth Elements in Graphite by Neutron Activation

Abstract: "A method is described for the identification and quantitative determination of trace amounts of rare earths in graphite by measurement of the energies and decays of the activities induced by neutron irradiation. The specific rare earth elements identified are europium and samarium. During the development of this method, the half-lives of Eu-152 and Sm-153 were determined. These are reported as 9.32 +/- 0.04 hours and 46.34 +/- 0.23 respectively."
Date: September 1, 1949
Creator: Ross, A. M.
System: The UNT Digital Library
Life of Van Stone Corrective Measures (open access)

Life of Van Stone Corrective Measures

This report is a document summarizing all information available on life aspects of various measures proposed to reduce or eliminate corrosion of Van Stone flanger.
Date: September 12, 1949
Creator: Botsford, C. W. & Eschbach, E. A.
System: The UNT Digital Library
Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin (open access)

Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin

Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."
Date: September 29, 1952
Creator: Schwope, A. D.; Muehlenkamp, G. T. & Chubb, Walston
System: The UNT Digital Library
Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin (open access)

Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin

Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."
Date: September 29, 1952
Creator: Schwope, A. D.; Muehlenkamp, G. T. & Chubb, Walston
System: The UNT Digital Library
The Application of Ceramics to Hanford Fuel Elements (open access)

The Application of Ceramics to Hanford Fuel Elements

From introduction: This work is a survey of possible uses of ceramic materials in Hanford-type fuel elements.
Date: September 4, 1953
Creator: King, B. W.; Tripp, H. P. & Duckworth, W. H.
System: The UNT Digital Library
Estimated Manufacturing Costs for the Recovery of Thorium and Uranium from Monazite Sand (open access)

Estimated Manufacturing Costs for the Recovery of Thorium and Uranium from Monazite Sand

Abstract: "Costs have been estimated for the production of uranium and pure thorium from monasite concentrates by a process involving (1) reaction of monasite with caustic soda, (2) dissolution of the hydrous oxides in hydrochloric acid, (3) separation from the bulk of the rare earths by hydroxide precipitation of thorium and uranium, and (4) purification by solvent extraction."
Date: September 15, 1950
Creator: Calkins, G. D. & Filbert, R. B., Jr.
System: The UNT Digital Library
Zirconium Pilot Plant Research and Development Progress Report (open access)

Zirconium Pilot Plant Research and Development Progress Report

The following progress report was compiled by the research and development division of the zirconium pilot plant. This report discusses two iodination and deposition runs that were completed as of August 20, 1951, as well as the third iodination run that uses a vaporizer condenser that condenses approximately 40 pounds of zirconium iodide.
Date: September 20, 1951
Creator: Accountius, O. E.; Black, D. G.; Dryden, C. E.; Finney, B. C.; Gruber, B. A.; Jurevic, W. G. et al.
System: The UNT Digital Library
Creep of 2S-O Aluminum Sheet at 500 and 550 C (open access)

Creep of 2S-O Aluminum Sheet at 500 and 550 C

Abstract: "Creep and creep-rupture tests were made on 25-O aluminum sheet at temperatures of 500 and 550 C. The estimated stresses that will produce 0.5 per cent deformation and rupture in 10,000 hours at 400, 450, 500, and 550 C (data at 400 and 450 C are from BMI-T-29, dated June 9, 1950) are presented."
Date: September 11, 1952
Creator: VanEcho, J. A.; Simmons, W. F. & Cross, H. C.
System: The UNT Digital Library
Instrumentation and Some Related Problems for Neutron Flux Measurement of the Los Alamos Scientific Laboratory Kiwi-A Reactor (open access)

Instrumentation and Some Related Problems for Neutron Flux Measurement of the Los Alamos Scientific Laboratory Kiwi-A Reactor

Abstract: "A description of the instrumentation for neutron flux measurement from Kiwi-A at NTS is given as some discussion of start-up considerations, detector design, system response adjustments, and power calibration of the reactor at some low level of power."
Date: September 1958
Creator: Barton, David M.; Helmick, Herbert H. & Jarvis, G. A.
System: The UNT Digital Library
Feasibility Study of a New Mass Flow System : Quarterly Report No. 5 Covering the Period from June 1, 1961 to August 31, 1961 (open access)

Feasibility Study of a New Mass Flow System : Quarterly Report No. 5 Covering the Period from June 1, 1961 to August 31, 1961

This is the fifth quarterly report that documents a system of mass flow that can record measurements of homogeneous flow, slurries, highly corrosive fluids and multiphase fluids, additionally considering pressure drops, measuring external to the flow, ruggedness and reliability.
Date: September 20, 1961
Creator: Haffner, J. W. & Genthe, William K.
System: The UNT Digital Library
Feasibility Study of a New Mass Flow System : Quarterly Report No. 1 Covering the Period From June 1 to September 1, 1960 (open access)

Feasibility Study of a New Mass Flow System : Quarterly Report No. 1 Covering the Period From June 1 to September 1, 1960

The following report describes a mass flow system that can measure homogeneous flow, slurries, highly corrosive fluids and multiphase fluids, with the addition of considering pressure drops, measuring external to the flow, ruggedness and reliability.
Date: September 21, 1960
Creator: Burgwald, G. M. & Genthe, William K.
System: The UNT Digital Library
Leakage Neutron Spectrum of  U²³³ Critical Assembly (open access)

Leakage Neutron Spectrum of U²³³ Critical Assembly

Abstract: "The leakage neutron spectrum of a U²³³ spherical critical assembly (Jezebel) has been measured using nuclear emulsions as radiator and detector. The spectrum obtained is compared with similar measurements on the U-235 and Pu-239 analogues of Jezebel U²³³; it is found to agree closely with that of the Pu-239 assembly and to be harder than that of the U-235 assembly. All three spectra are compared with theoretical spectra obtained from a numerical approximation to the neutron transport equation."
Date: September 1962
Creator: Bobisud, Larry E.
System: The UNT Digital Library
A Monte Carlo Calculation of the Neutron Detection Efficiency of a Hydrogen Bubble Chamber (open access)

A Monte Carlo Calculation of the Neutron Detection Efficiency of a Hydrogen Bubble Chamber

Abstract: "The calculation of the efficiency of the Los Alamos hydrogen bubble chamber for detection of neutrons in the energy range 5 to 35 MeV has been done using a "Monte Carlo" technique. The detection efficiency is calculated as a function of energy of the neutron and angle of the proton recoil."
Date: September 1962
Creator: Wooten, J. K. & Bryant, H. C.
System: The UNT Digital Library
Uranium Migration in UOâ‚‚-Bearing Ceramics (open access)

Uranium Migration in UOâ‚‚-Bearing Ceramics

This report follows a preliminary study on uranium migration in pressed and sintered UO2-bearing bodies based on MoSi2 or Al2O3.
Date: September 4, 1953
Creator: Quirk, J. F.; Smalley, A. K.; Duckworth, W. H. & Ferrell, Edward Francis.
System: The UNT Digital Library
Differential Thermal-Expansion Effects on Brazed Joints (open access)

Differential Thermal-Expansion Effects on Brazed Joints

Abstract: "Differential thermal-expansion effects in brazed joints involving Type 310 stainless steel and GE-62 brazing alloy were investigated. The work included dilation and modulus-of-elasticity measurements using homogenous cast specimens and observations on bimetallic cantilevers made of the two constituents. No anomalies were found, although there were irregularities in the expansion of the brazing alloy which were ascribed to a solubility phenomenon. The elastic modulus of the brazing alloy was determined. Cantilever deflections with temperature and with load were measured, and the results were interpreted using equations which treat the specimens as true bimetals consisting of two homogeneous components. The difference in thermal-expansion coefficients obtained in this way from the temperature-deflection data was consistent with the dilation measurements. The load measurements yielded an average elastic modulus for the bimetal which was about two-thirds of what would have been expected from knowledge of the components. This discrepancy probably arose from porosity which was observed in the braze components."
Date: September 4, 1953
Creator: Saller, Henry A.; Baroody, Eugene Michael, 1914-1982; Deem, H. W.; Stacy, J. T. & Klebanow, H. L.
System: The UNT Digital Library
Fused Salt Mixtures as Potential Liquid Fuels for Nuclear Power Reactors (open access)

Fused Salt Mixtures as Potential Liquid Fuels for Nuclear Power Reactors

From introduction: "This report summarizes the work done on a study of fused-salt systems in a search for new liquid fuels suitable for use in a nuclear power reactor."
Date: September 8, 1953
Creator: Crooks, R. C.; Snyder, M. J. & Clegg, J. W.
System: The UNT Digital Library
Investigation of the Behavior of NaOH-UO₃ Slurries in Small Flow Loops (open access)

Investigation of the Behavior of NaOH-UO₃ Slurries in Small Flow Loops

From introduction: "This report presents the results of an experimental program to evaluate engineering problems which might be encountered when circulating NaOH-UO3 slurry through a thermal cycle."
Date: September 15, 1953
Creator: Stang, J. H.; Lagedrost, J. F.; Simons, E. M. & Dayton, R. W.
System: The UNT Digital Library
Plastic Deformation in Grooved Rolls (open access)

Plastic Deformation in Grooved Rolls

This report covers a study of the deformation characteristics of uranium in grooved rolls. The study's purpose was to provide a basis for possible improvements in the uniformity of the rolled rod produced for the Hanford and Savannah River reactors.
Date: September 27, 1955
Creator: Saller, Henry A.; Keeler, John R. & Cuddy, Lee J.
System: The UNT Digital Library
The Mechanical Properties of Beta-Quenched Uranium at Elevated Temperatures (open access)

The Mechanical Properties of Beta-Quenched Uranium at Elevated Temperatures

The creep strength and tensile properties-were determined in vacuum for beta-quenched, derby uranium. The stresses to produce a secondary creep rate of- 0.0001 per cent per hr at 100, 250, 400, and 500 deg C were 48,000, sile strengths were 114,500, 35,100, 11,100, and 8,500 psi at temperatares of 28, 300, 500, and 700 deg C, respectively. The creep and tensile strengths decrease quite rapidly with increasing temperature in the temperatare range 250 to 400 deg C.
Date: September 6, 1955
Creator: Shober, Frederic R.; Marsh, Lyle L. & Manning, G. K.
System: The UNT Digital Library
High-Boron Steels for Reactor Shielding (open access)

High-Boron Steels for Reactor Shielding

This report follows work performed to determine the effects of large boron additions on the fabricability and room-temperature tensile properties of various steels for reactor shielding.
Date: September 27, 1955
Creator: Saller, Henry A.; Stacy, John T. & Klebanow, Herbert L.
System: The UNT Digital Library
Neutron Production by High-Energy Particles (open access)

Neutron Production by High-Energy Particles

Abstract: "From neutron-yield measurements made with a MnSO4 detecting solution, the average number of neutrons produced per inelastic event is determined for a series of elements from lithium to uranium for 340-Mev protons, 190-and 315-Mev deuterons, 490-Mev He3 ions, and 90- and 160-Mev neutrons. The results are analyzed in an attempt to understand the total yield measurements for thick targets and to explain the variation of yield with the atomic number of the target."
Date: September 29, 1954
Creator: Crandall, Walter E. & Millburn, George P.
System: The UNT Digital Library
Use of Controlled Photosynthesis for Maintenance of Gaseous Environment (open access)

Use of Controlled Photosynthesis for Maintenance of Gaseous Environment

Abstract: "The problem of maintaining livable oxygen and carbon dioxide pressures in a closed space in which men must live leads to consideration of the possible use of the photosynthesis of green algae. A calculation based on the known respiratory rate of man and the photosynthetic rates of Chlorella indicates that it would be feasible to use algae for this purpose."
Date: September 1954
Creator: Bassham, James Alan
System: The UNT Digital Library
Metallurgical Evaluation of the Uranium Rods Rolled for the Chalk River Pile Test (open access)

Metallurgical Evaluation of the Uranium Rods Rolled for the Chalk River Pile Test

Summary: "The laboratory data collected during the metallurgical evaluation of these rods indicate that lower rolling temperatures increased the ultimate and yield strength, the amount of cold work, and the degree of preferred orientation existing in these uranium rods."
Date: September 11, 1952
Creator: Sanderson, M. J. & Hueschen, R. E.
System: The UNT Digital Library
Criticality Conditions for 1.75 Per Cent Enriched Uranium Slugs (open access)

Criticality Conditions for 1.75 Per Cent Enriched Uranium Slugs

Abstract: "A batch of slugs is being prepared for which the U-235 content will be 1.75 per cent, and it is of interest to calculate the minimum number of such slugs required for a critical assembly in water. Using Handbook (CL-697) methods, a critical assembly of these slugs arranged in a lattice with a spacing of 5.5 cm."
Date: September 11, 1952
Creator: Erkman, John O.
System: The UNT Digital Library