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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.
Object Type: Report
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.
Object Type: Report
System: The UNT Digital Library
Stepwise Calculation for the Determination of the Number of Transfer Units in Countercurrent Extraction Columns (open access)

Stepwise Calculation for the Determination of the Number of Transfer Units in Countercurrent Extraction Columns

Report discussing a method for the stepwise calculation of the number of transfer units utilized in a given solvent extraction operation. "Use of the method results in a very appreciable saving in time of calculation with an error of 1.5% for the runs tested. The error tends to become smaller with increasing total numbers of transfer units involved."
Date: September 12, 1949
Creator: Burns, W. A. & Eschbach, E. A.
Object Type: Report
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
Object Type: Report
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
Object Type: Report
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.
Object Type: Report
System: The UNT Digital Library
Boron stainless steel for drop rods (open access)

Boron stainless steel for drop rods

From introduction: "The present investigation of the properties of boron stainless steel is an outgrowth of a project started in 1947. The problem is to replace the present steel used for drop rods in the Hanford piles with a material much less subject to corrosive attack from the humid atmosphere existing at the location of the rods."
Date: September 7, 1948
Creator: Callen, A. C. & Heckman, A. L.
Object Type: Report
System: The UNT Digital Library
Final Report on Recovery of Thorium and Uranium From Monazite Sand : Volume 1 (open access)

Final Report on Recovery of Thorium and Uranium From Monazite Sand : Volume 1

Report describing a method for recovery of high yields of thorium and uranium from monazite sand concentrates. Monazite is decomposed into hydrous metal oxides, which are dissolved in an acid. The solution is then separated into a precipitate, which seperates from thorium and uranium. An alternate separation method is evaluated.
Date: September 15, 1950
Creator: Calkins, G. D.; Filbert, R. B., Jr.; Bearse, A. E. & Clegg, J. W.
Object Type: Report
System: The UNT Digital Library
Final Report on Recovery of Thorium and Uranium From Monazite Sands, Volume 2 (open access)

Final Report on Recovery of Thorium and Uranium From Monazite Sands, Volume 2

From abstract: "Details are presented on the processing of monazite sand and on separating the rare earths from thorium and uranium. Solvent-extraction and ion-exchange techniques for purifying thorium and uranium are described."
Date: September 15, 1950
Creator: Calkins, G. D.; Filbert, R. B., Jr.; Bearse, A. E. & Clegg, J. W.
Object Type: Report
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.
Object Type: Report
System: The UNT Digital Library
Progress Report on Refining of MgX and Other Uranium-Bearing Materials (open access)

Progress Report on Refining of MgX and Other Uranium-Bearing Materials

From abstract: "The effects of solution concentration and acidity on extraction of uranium by diethyl ether have been investigated... The approximate solubility of vanadium pentoxide in nitric acid was determined."
Date: September 30, 1950
Creator: Ewing, R. A.; Belcher, R. L.; Kiehl, S. J., Jr. & Bearse, A. E.
Object Type: Report
System: The UNT Digital Library
Progress Report on Refining of MgX and Other Uranium-Bearing Materials (open access)

Progress Report on Refining of MgX and Other Uranium-Bearing Materials

From abstract: "Results are presented which suggest the possibility of satisfactorily extracting uranium from pitchblende feeds with neutral ether, without the necessity of removing sulfate, by the addition of a sufficient quantity of iron to the feed." Other factors' effects on extraction were tested and arsenic was traced throughout extraction.
Date: September 30, 1951
Creator: Ewing, R. A.; Kiehl, S. J., Jr.; Bearse, A. E. & Sharpe, R. E.
Object Type: Report
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.
Object Type: Report
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.
Object Type: Report
System: The UNT Digital Library
Preliminary Investigation of a Five-Crystal Scintillation Gamma-Ray Spectrometer (open access)

Preliminary Investigation of a Five-Crystal Scintillation Gamma-Ray Spectrometer

Abstract: A five-crystal scintillation gamma-ray spectrometer was constructed for use as a Compton coincidence spectrometer or as a pair coincidence spectrometer. Preliminary tests are discussed. The efficiency in either mode of operation was found to be low; however, the backgrounds were favorable and good definition of characteristic lines was achieved...Future tests and plans for improvements are discussed."
Date: September 1958
Creator: Mills, Roger E. & Kloepper, Robert M.
Object Type: Report
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.
Object Type: Report
System: The UNT Digital Library
Some Reactor Physics in the Rover Project (open access)

Some Reactor Physics in the Rover Project

From abstract: "A general and systematic development of reactor computing methods and detailed application given in Report LAMS-2255 separately is supplemented in this report for a few specific systems of interest to the Rover program. Neutron cross sections, reactor description, and computed results are given for a reactor required to have a constant (radially) power distribution at high temperatures."
Date: September 1958
Creator: Mills, C. B.
Object Type: Report
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.
Object Type: Report
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.
Object Type: Report
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.
Object Type: Report
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.
Object Type: Report
System: The UNT Digital Library
Progress Relating to Civilian Applications During August, 1956 (open access)

Progress Relating to Civilian Applications During August, 1956

Report discussing the progress of research projects at Battelle Memorial Institute relating to civilian applications during August 1956.
Date: September 4, 1956
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Object Type: Report
System: The UNT Digital Library
Uranium Migration in UO₂-Bearing Ceramics (open access)

Uranium Migration in UO₂-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.
Object Type: Report
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.
Object Type: Report
System: The UNT Digital Library