Welding of High-Strength Stainless Steels for Pressure Vessels (open access)

Welding of High-Strength Stainless Steels for Pressure Vessels

The following report describes the welding characteristics of several high-strength stainless steels that were considered for use as a pressure vessel to operate at high pressures at 800 F.
Date: April 5, 1954
Creator: Vagi, J. J.; Thompson, V. R. & Martin, D. C.
Object Type: Report
System: The UNT Digital Library
Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Ternary Additions (open access)

Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Ternary Additions

Abstract: "Refinement of grain size of the base uranium-chromium eutectic alloy (uranium-5 w/o chromium) by ternary additions is discussed. Thirteen additions to the base alloy were investigated, and three additions were found to exhibit worthwhile grain-refinement tendencies. The three alloys, uranium-5 w/o chromium-0.2 w.o molybdenum, uranium-5 w/o chromium-0.2 w/o germanium, and uranium-5 w/o chromium-0.2 w/o niobium, were heat treated to produce final grain-size structures of between 0.015 and 0.033 mm."
Date: July 5, 1955
Creator: Saller, Henry A.; Dickerson, Ronald F.; Murr, William E. & Bauer, Arthur A.
Object Type: Report
System: The UNT Digital Library
Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1952 (open access)

Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1952

This quarterly progress report details ongoing work at the Oak Ridge National Laboratory as part of the Aircraft Nuclear Propulsion Project. Topics of discussion include reactor theory and design, shielding research, materials research, appendixes with information on ongoing analytical chemical studies.
Date: August 5, 1952
Creator: Briant, R. C.; Buck, J. H.; Miller, A. J. & Cottrell, W. B.
Object Type: Report
System: The UNT Digital Library
Decontamination of ORNL Purex Pilot Plant (open access)

Decontamination of ORNL Purex Pilot Plant

From abstract: "This report describes the decontamination of Oak Ridge National Laboratory Purex Pilot Plant facilities and presents an appraisal of the decontaminating techniques and reagents which were employed."
Date: May 5, 1952
Creator: Wood, H. P.
Object Type: Report
System: The UNT Digital Library
The Masses of Identified Positive Heavy Mesons (open access)

The Masses of Identified Positive Heavy Mesons

The following report describes the charged secondary particles from all presently known decay modes of positive K mesons that have been identified, and the masses of the primaries measured by the momentum-range method.
Date: April 5, 1956
Creator: Peterson, James Ray
Object Type: Thesis or Dissertation
System: The UNT Digital Library
Analysis of Bevatron Tau Mesons (open access)

Analysis of Bevatron Tau Mesons

The following document analyzes one hundred and seventy-seven bevatron tau mesons for Q value of the tau decay, tau spin and parity, and possible polarization effects.
Date: November 5, 1956
Creator: Haddock, Roy Phillip, 1928-
Object Type: Thesis or Dissertation
System: The UNT Digital Library
Nitration Reactions of Shell Spray Base under Purex Waste Recovery Process Conditions (open access)

Nitration Reactions of Shell Spray Base under Purex Waste Recovery Process Conditions

Abstract: "Experiments were performed to characterize the types of nitro compounds that might be formed by reaction of Shell Spray Base with nitric acid, to determine the extent of their formation, if any, and their path under conditions of nitric acid recovery in the Purex Process. It is concluded that the instability of Shell Spray Base to nitration, under conditions to prevail in the plant, presents neither a disposal problem nor a safety problem."
Date: December 5, 1952
Creator: Wagner, R. M.
Object Type: Report
System: The UNT Digital Library
Interim Report on Examination of Powder Metallurgy Slug from PT-105-313-4M (open access)

Interim Report on Examination of Powder Metallurgy Slug from PT-105-313-4M

This report examines a uranium slug that has been produced by powder metallurgical methods and exposed in the 100-DR Pile and was deformed during pile exposure.
Date: January 5, 1953
Creator: O'Keefe, D. P.
Object Type: Report
System: The UNT Digital Library
Applied Potential Corrosion of Aluminum : Final Report (open access)

Applied Potential Corrosion of Aluminum : Final Report

Report describing data resulting from dynamic tests to determine applied potential corrosion of aluminum.
Date: December 5, 1955
Creator: Sanborn, Kenneth L.
Object Type: Report
System: The UNT Digital Library
Neutron Diffusion and Random Walk (open access)

Neutron Diffusion and Random Walk

The following report analyzes random walks and whether or not they can be used to shed any light on problems of neutron diffusion.
Date: February 5, 1953
Creator: Duvall, G. E.
Object Type: Report
System: The UNT Digital Library
Ionization Equilibrium Equation of State (open access)

Ionization Equilibrium Equation of State

Abstract: "A simple solution to Saha's equation has been obtained. The method of solution involves iteration with respect to the electron pressure or concentration and can be applied to the simultaneous calculations of any number of ions. Sample results are given for lithium and aluminum."
Date: October 5, 1959
Creator: Rouse, Carl A.
Object Type: Report
System: The UNT Digital Library
Removal of Deuterated Boric Acid From Deuterium Oxide Solution by Ion Exchange Resin (open access)

Removal of Deuterated Boric Acid From Deuterium Oxide Solution by Ion Exchange Resin

Introduction: "Because of the importance of the value of the transport mean free path of thermal neutrons in deuterium oxide, Kash and Woods proposed to redetermine this value in deuterium oxide (99.4 atom-percent deuterium, by an extrapolation method. Kash and Woods thought that the low value of the transport mean free path might be a source of error. This paper relates studies of procedures by which (1) boron material would be dissolved in high content deuterium oxide without adding foreign atoms, particularly hydrogen atoms which might adversely affect the test, (2) the boron content of the deuterium oxide solvent may be determined, (3) ion exchangers may be deuterized and de-deuterized, and (4) ion exchange may remove specific ions from solution."
Date: January 5, 1954
Creator: Silverman, L.
Object Type: Report
System: The UNT Digital Library
An Ion Chamber for the Determination of Small Amounts of Tritium in Other Gases (open access)

An Ion Chamber for the Determination of Small Amounts of Tritium in Other Gases

This report helps determine tritium in the range of 0.1 to 100% in other gases using an ion chamber that is analyzed within this report.
Date: May 5, 1951
Creator: Mattraw, H. C.
Object Type: Report
System: The UNT Digital Library
On the Reaction p + d [right arrow] [mu]⁺ + t (open access)

On the Reaction p + d [right arrow] [mu]⁺ + t

Abstract: "The cross section for this reaction is calculated for three Hulthen deuteron wave functions. A hard core in the deuteron at one-half meson Compton wavelength reduces the total cross section and flattens the angular distribution in the backwards direction in agreement with experiment."
Date: February 5, 1954
Creator: Bludman, Sidney A.
Object Type: Report
System: The UNT Digital Library
Extraction of Zirconium and Hafnium with Various Fluorinated [beta]-Diketones (open access)

Extraction of Zirconium and Hafnium with Various Fluorinated [beta]-Diketones

Abstract: "The distribution ratios and equilibrium constants for the extraction of zirconium and hafnium from 4 M perchloric acid with various combinations of fluorinated [beta]-diketones and organic solvents have been determined. The separation factors K'Zr/K'HF, found for this acidity were: Z-thenoyltrifluoroacetone in benzene, 25; Z-thenoyltrifluoroacetone in o-dichlorobenzene, 16; benzoyltrifluoroacetone in benzene, 18; isovaleroyltrifluoroacetone in benzene, 13; isovaleroyltrifluoroacetone in n-hexane, 13."
Date: April 5, 1954
Creator: Huffman, E. H.; Iddings, G. M; Osborne, R. N. & Shalimoff, G. V.
Object Type: Report
System: The UNT Digital Library
Corrosion of Austenitic Stainless Steel in Mixed Acids (open access)

Corrosion of Austenitic Stainless Steel in Mixed Acids

Introduction:"A corrosion test program in support of the Redox Project was carried out during the second quarter of 1950 to determine the corrosion rates of several austenitic stainless steels in simulated 202-B Waste Storage solution containing HF, HN03, and H2SO4 acids. The results of this program are contained herein and all original data are recorded in laboratory notebook HW-3282-T."
Date: June 5, 1950
Creator: Koenig, W. W.
Object Type: Report
System: The UNT Digital Library
Chemical Development Section C Monthly Progress Report July 1959 (open access)

Chemical Development Section C Monthly Progress Report July 1959

Nitrate contained in raffinates from Canadian Blind River mills interferes seriously with thorium extraction by secondary amines. With primary amines, however, the effect is negligible and these compounds are the preferred process extractants.
Date: August 5, 1959
Creator: Brown, K. B.; Allen, K. A.; Blake, C. A.; Coleman, C. F.; Crouse, D. J.; Ryon, A. D. et al.
Object Type: Report
System: The UNT Digital Library
Temperature and Rate of Heat Removal of UO2 Test Elements (open access)

Temperature and Rate of Heat Removal of UO2 Test Elements

The method of calculation of various quantities relating the temperature and the rate of heat removal of UO2 test elements is presented. Graphs of the appropriate quantities as a function of the rate of heat removal are included.
Date: August 5, 1959
Creator: Perry, A. M.
Object Type: Report
System: The UNT Digital Library
Calculation of Transport Cross Sections (open access)

Calculation of Transport Cross Sections

Many elements exhibit anisotropic scattering at energies of interest in reactor calculations. A method is presented for the calculation of transport cross sections including the observed anisotropy.
Date: August 5, 1959
Creator: Nestor, C. W.
Object Type: Report
System: The UNT Digital Library
Feasibility Study of a Neutron Flux Bolometer (open access)

Feasibility Study of a Neutron Flux Bolometer

Abstract: "A small low impedance flux monitoring device has been built which utilizes the heating (and consequent chance in resistance) of a boron coated platinum wire. Feasibility tests in the Argonne-GP-3 reactor indicate that it may develop into a wide range instrument, particularly useful at high flux levels. Design and constructional details of the bolometer and its associated circuits are given. The circuitry is somewhat unique since it is in effect an all electronic self-balancing bridge. Future lines of research are suggested to solve some of the remaining problems."
Date: September 5, 1951
Creator: Leonard, Robert R.
Object Type: Report
System: The UNT Digital Library
The Uranium-Titanium Alloy System (open access)

The Uranium-Titanium Alloy System

Abstract: "A uranium-titanium constitution diagram is presented. There is complete solid solubility between titanium and gamma uranium above about 2100 F. Only one compound exists in the system. It has a hexagonal structure based on U2Ti. It has a fairly wide range of stability, particularly on the titanium side. Beta-titanium solid solution decomposes eutectoidally into alpha titanium and compound at 1150 F. Eutectoid composition is about 72 atomic per cent titanium. Gamma-uranium solid solution decomposes eutectoidally at 1325 F into beta uranium and compound. Eutectoid composition is about 6 atomic per cent titanium. Beta uranium and compound react peritectoidally at 1233 F to give alpha uranium. Solubility of titanium in alpha and beta uranium is low as is the solubility or uranium in alpha titanium."
Date: November 5, 1952
Creator: Udy, Murray C. & Boulger, Francis W.
Object Type: Report
System: The UNT Digital Library
Neutron Total Cross Section for Bismuth and Uranium Between 45 and 160 Mev (open access)

Neutron Total Cross Section for Bismuth and Uranium Between 45 and 160 Mev

"Neutron total cross sections for bismuth and uranium have been measured in a good geometry transmission experiment, using a time-of-flight instrumentation. The source of neutrons was the stripped deuteron beam of the 184-inch synchrocyclotron. The results are shown in Fig. 1. Uncertainties are shown in terms of standard deviations, due to counting statistics only, and to energy channel width."
Date: August 5, 1953
Creator: Linlor, William I., 1915- & Ragent, Boris
Object Type: Report
System: The UNT Digital Library
Analysis of Lid Tank Neutron Data for Lead and Iron (open access)

Analysis of Lid Tank Neutron Data for Lead and Iron

Abstract: An analysis of the lid tank neutron data for Pb-H2O and Fe-H2O is made. "Effective" fast neutron cross sections for the metals are obtained. This is based on the "one collision theory" of shielding. Values are 3.4 barns for Pb and 2.0 barns for Fe. These compare very well with those obtained by Albert and Welton based on other lid tank data and another method of calculation.
Date: January 5, 1951
Creator: Podgor, S.
Object Type: Report
System: The UNT Digital Library
Factors Affecting Properties of Extruded Compacts of Crystal Bar Zirconium (open access)

Factors Affecting Properties of Extruded Compacts of Crystal Bar Zirconium

The following report analyzes various experiments made to discover factors that may affect properties of extruded compacts of crystal bar zirconium.
Date: December 5, 1955
Creator: Arnold, Samuel V.
Object Type: Report
System: The UNT Digital Library