The Determination of Total Plutonium in the Presence of Aluminum (open access)

The Determination of Total Plutonium in the Presence of Aluminum

Introduction: "The adoption of aluminum nitrate as salting agent in the Redox process made it imperative that a method be available for determining plutonium in the presence of aluminum. However, large amounts of aluminum have been found to interfere with the determination of plutonium by the lanthanum fluoride procedure. Previous attempts to increase the accuracy of the lanthanum fluoride method, by precipitating LaF3 from 4 M HF (rather than 2 M), have been successful only when the initial plutonium level was high."
Date: February 10, 1950
Creator: Burns, R. E. & Barton, G. B.
System: The UNT Digital Library
Chemical Research Section Progress Report for January 1950 (open access)

Chemical Research Section Progress Report for January 1950

The following documents are progress reports that follow chemical research studies in subjects such as ruthenium tetroxile distillations, extraction-scrub studies of zirconium and niobium, and oxidation of plutonium and stabilization of plutonium(VI) during extraction of IAF solutions.
Date: February 15, 1950
Creator: Albaugh, F. W.
System: The UNT Digital Library
Corrosion of Austenitic Stainless Steel Type 347 in Redox Process Stream : (ORNL #1 Flowsheet) (open access)

Corrosion of Austenitic Stainless Steel Type 347 in Redox Process Stream : (ORNL #1 Flowsheet)

The following report provides the results of laboratory corrosion tests held to investigate the behavior of austenitic stainless steel, Type 347, in selected O.R.N.L. #1 Redox streams.
Date: February 23, 1950
Creator: Koenig, W. W.
System: The UNT Digital Library
Diameter Measurements of Slugs Before and After Prolonged Heat Treatment (open access)

Diameter Measurements of Slugs Before and After Prolonged Heat Treatment

Abstract: "Diameter measurements of 25 slugs taken before and after a prolonged heat treatment showed no evidence of differences that would indicate blistering. The average effects of the treatment was different for the various slugs. Large differences in diameter measurements between slugs. Large differences in diameter between slugs and significant differences between indices and positions were found."
Date: February 16, 1948
Creator: Bennett, Carl A. & Lane, J. J.
System: The UNT Digital Library
Improved Zirconium Alloys : Summary Report, April 1, 1960 - January 31, 1961 (open access)

Improved Zirconium Alloys : Summary Report, April 1, 1960 - January 31, 1961

Abstract: "The objectives of this program are the development of zirconium-base alloys possessing exceptionally good corrosion resistance to 680 F water or 750-900 F system and/or improved strength at elevated temperatures. Approximately 100 binary compositions were prepared and screened by corrosion testing in 680 F water; selected compositions were exposed to 750 F steam. The data obtained indicate promising bases for ternary and quaternary alloys. Related investigations involving zirconium purity and heat treatment for improvement of corrosion properties are proceeding. Hydrogen pickup and mechanical properties will be used as acceptability tests on promising compositions."
Date: February 28, 1961
Creator: Weinstein, Daniel; Holtz, F. C. & Van Thyne, R. J.
System: The UNT Digital Library
The Boron-Carbon System: Quarterly Report Number 3, November 1960 - January 1961 (open access)

The Boron-Carbon System: Quarterly Report Number 3, November 1960 - January 1961

Abstract: A definitive investigation of the boron-carbon equilibrium system is being made by X-ray diffraction, metallographic, and thermal analytical techniques. On the basis of metallographic and X-ray diffraction studies it is concluded that boron carbide has a range of solubility from approximately 10 to 20 atomic per cent carbon at 1500 degrees to 2000 degrees Celsius. The melting point of the carbide-graphite eutectic has been established as 2325-2350 degrees Celsius. No reversible allotropy of the beta-rhombohedral structure has been observed. The solubility of carbon in boron is very small. The melting point of dilute carbon alloys is found to be essentially the same as that of pure boron (2040 degrees to 2050 degrees). No metallographic evidence of a three-phase reaction of dilute alloys is observed.
Date: February 6, 1961
Creator: Elliott, Rodney P.
System: The UNT Digital Library
Mineralogical Examination of Pitchblende Concentrates and Nitric Acid Digest Residues (open access)

Mineralogical Examination of Pitchblende Concentrates and Nitric Acid Digest Residues

This report has two parts to it discussing mineralogical examination of pitchblende concentrates and nitric acid digest residues. Part I gives the results of a cursory examination with the petrographic microscope of samples of pitchblende concentrates and residues to see if there is a relationship between the mineral composition of the samples and the filterability of the residue. Part II gives a revaluation of the data in Report BMI-241 on the mineral composition of two residues from the nitric acid digestion of pitchblende concentrates at the Rallinckrodt Chemical Works.
Date: February 9, 1951
Creator: Scott, D. W.; Tangel, O. F. & Richardson, A. C.
System: The UNT Digital Library
Feasibility Study of a New Mass Flow System : Covering the Period from January 1 to January 31, 1961 (open access)

Feasibility Study of a New Mass Flow System : Covering the Period from January 1 to January 31, 1961

This document reports progress during the month of February, 1961, recording investigations and studies of a flow rate using a curved pipe or S-tube and documenting measurements of mass flow, tube design and construction.
Date: February 15, 1961
Creator: Burgwald, G. M.; Stone, C. A. & Genthe, William K.
System: The UNT Digital Library
Improved Zirconium Alloys Quarterly Report: October - December 1960 (open access)

Improved Zirconium Alloys Quarterly Report: October - December 1960

Quarterly report describing the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between October 1 to December 31, 1960 and was conducted by the United States and the European Atomic Energy Community (EURATOM).
Date: February 2, 1961
Creator: Weinstein, Daniel; Holtz, F. C. & Van Thyne, R. J.
System: The UNT Digital Library
Improved Zirconium Alloys Annual Report: 1961 - 1961 (open access)

Improved Zirconium Alloys Annual Report: 1961 - 1961

Annual technical report describing the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between February 1, 1961 to February 28, 1962 and was conducted by the United States and the European Atomic Energy Community (EURATOM).
Date: February 28, 1962
Creator: Weinstein, Daniel & Holtz, F. C.
System: The UNT Digital Library
Degradation Products of Tributyl Phosphate (open access)

Degradation Products of Tributyl Phosphate

Abstract: "A method for determination of dibutyl phosphate in solvent streams containing tributyl phosphate is outlined. The method is based on analysis for total uranium of total phosphate after removal of uranium and phosphate in excess of that present as uranyl dibutyl phosphate. Results on plant solvent samples are presented. Difficulties with precipitation of [...] dibutyl phosphate, when fresh solvents were employed, are discussed. Small amounts of nonphosphate uranium-complexing agents were found in plant solvents. Diluent degradation is postulated as the source of these components. Emulsion-formation tendencies appeared to correlate better with concentrations of these contaminants than with dibutyl phosphate content."
Date: February 17, 1956
Creator: Ewing, Robert A.; Kiehl, Samuel J. & Bearse, Arthur E.
System: The UNT Digital Library
Design Studies on Cesium-137 as a Source for High Level Gamma Irradiators: Quarterly Progress Report Number 2, September - December 1959 (open access)

Design Studies on Cesium-137 as a Source for High Level Gamma Irradiators: Quarterly Progress Report Number 2, September - December 1959

Quarterly progress report describing work related to a study of radiation physics problems involved in the design of high-level cesium-137 gamma sources. It outlines work completed and ongoing goals for the project.
Date: February 29, 1960
Creator: Voyvodic, L.
System: The UNT Digital Library
Magnetic Recorder for Nuclear Pulse Application : Covering the Period from December 6, 1959 to February 5, 1960 (open access)

Magnetic Recorder for Nuclear Pulse Application : Covering the Period from December 6, 1959 to February 5, 1960

"Abstract: An evaluation of a modulator flux sensitive playback head to be used with an analog magnetic recorder for nuclear pulse information storage was made. The modulator head was found unsultable. A pulse stretching unit was constructed which takes pulses from a standard linear pulse amplifier and provides an output signal suitable for driving a recording head."
Date: February 24, 1960
Creator: Burgwald, G. M.
System: The UNT Digital Library
A Microdetermination of Uranium by Ferric Sulfate Titration (open access)

A Microdetermination of Uranium by Ferric Sulfate Titration

Abstract: "Following nitrate removal by means of a three-stage hydrochloric acid digestion, uranium was reduced with chromous sulfate reagent. In an inert atmosphere, the quadrivalent uranium was titrated at 80-95[degrees] with standard ferric sulfate solution. The end point was obtained with a potentiometric cell including a platinum in-titrant reference electrode and a platinum indicator electrode. Application was made to various low leverl uranium solutions. For samples containing 1 - 12 milligrams or uranium, less than one percent error may be expected. Iron and chromium do not interfere."
Date: February 16, 1949
Creator: Christopherson, E. W.
System: The UNT Digital Library
Corrosion Tests on Tantalum, Hastelloy C and Duriron in 234-5 Project Solutions (open access)

Corrosion Tests on Tantalum, Hastelloy C and Duriron in 234-5 Project Solutions

Introduction: "Room temperature and elevated temperature, static immersion and vapor suspicion, corrosion tests were conducted with Duriron, Hastelloy C, and tantalum in hydriotic acid and 234-5 project process supernatant solution (synthetic environments. The data relevant to these tests are contained herein."
Date: February 25, 1949
Creator: Work, J. B. & Koenig, W. W.
System: The UNT Digital Library
High Energy Fission and Spallation of Uranium (open access)

High Energy Fission and Spallation of Uranium

From introduction: "This report is an attempt to examine, semiquantitavely, the way the competition between neutron emission and fission varies for heavy nuclei as a function of nuclear type and excitation energy. Many of the ideas herein are the results of discussions with R. H. Goeckermann and W. Heckrotte of the University of California Radiation Laboratory."
Date: February 25, 1954
Creator: Batzel, Roger Elwood
System: The UNT Digital Library
The Elimination of Microwave Reflections (open access)

The Elimination of Microwave Reflections

Abstract: "The reflections of microwaves from the walls of a plasma-containing vessel are studied. The probable cause of the reflections is discussed, and several suggestions are made for eliminating the reflections from the waveguide in the vessel and particularly from the pyrex vessel wall and copper tubing surrounding the pyrex. Quarter-wave-thick carbon-filled plastics or glasses having a very low vapor pressure room most promising when placed inside the pyrex cylinder. BaTiO3 appears to be an excellent material when placed outside the vacuum."
Date: February 1, 1955
Creator: Beard, David
System: The UNT Digital Library
Effect of a Decelerating Grid on Current from an Ion Source (open access)

Effect of a Decelerating Grid on Current from an Ion Source

Abstract: "A theoretical criterion is given for the conditions under which the ions from an ion source may be decelerated by a decelerating grid, following the accelerating grid which extracts ions from the emitter, without causing a reduction in the current supplied by the source."
Date: February 23, 1955
Creator: Bing, George F., 1924-; Gardner, C. S. & Northrop, Theodore G.
System: The UNT Digital Library
The Valve Actuated Pulse Column Design (open access)

The Valve Actuated Pulse Column Design

Abstract: "The valve-actuated pulse column is employed to give phase separation on each half cycle in the countercurrent flow cycle and provides independent control over each step in the cycle. The dependence on temperature of operation, on pulse frequency and amplitude, and on plate design and spacing has been studied for extraction and stripping of uranium with tributyl phosphate in a hydrocarbon diluent. It is found that the efficiency increases quite significantly as the temperature is raised regardless of the direction of transfer and this increased efficiency is accompanied by greater operational freedom. A decrease in hole size, decrease in plate separation and increase in frequency all lead to higher efficiency in agreement with the concept that small drops continually formed coalesced and reformed, lead to maximum interphase transfer. The high extraction efficiency of the column is probably aided further by the relatively sharp pulse produced."
Date: February 16, 1953
Creator: Burger, L. L. & Clark, L. H.
System: The UNT Digital Library
Beehive and Hornet : Reactor Codes for Spherical Geometry (open access)

Beehive and Hornet : Reactor Codes for Spherical Geometry

Abstract: Beehive is a five energy group, two region, time independent spherical reactor code. It considers the problem of reactor system in which the core material is assumed to be at a higher energy (temperature) than the reflector material. The code obtains a closed solution for the critical reactor assembly by a procedure which is a logical extension of normal two group theory. The companion code, Hornet, computes the neutron fluxes for the critical assembly determined by the Beehive calculation. Both codes have been programmed for the IBM Magnetic Drum Data-Processing Machine, Type 650. The codes, together with the flow diagrams, are included with this report.
Date: February 8, 1957
Creator: Stone, Stuart P.
System: The UNT Digital Library
A High-Current Radio-Frequency Ion Accellerator (open access)

A High-Current Radio-Frequency Ion Accellerator

Abstract: "A radio-frequency ion accelerator is described which is capable of continuous currents of protons of 250 ma at an energy of 500 kev. The beam is less than 3 in. in diameter and has a divergence of less than 2 degree half angle. Operation of the machine accelerating deuterons to an energy of 1000 kev is also described."
Date: February 1957
Creator: Lamb, William A. S.; Hester, Ross E. & Kippenhan, Dean O.
System: The UNT Digital Library
A Description of a Shock Wave in Free Particle Hydrodynamics with Internal Magnetic Fields (open access)

A Description of a Shock Wave in Free Particle Hydrodynamics with Internal Magnetic Fields

Abstract: "The structure of an extremely strong magnetohydrodynamic shock is discussed in the limit of no particle collisions. It is tentatively concluded that the shock transition takes place through the mechanism of a strong electric field produced by charge separation. The pressure in the shocked plasma is due primarily to a very high electron temperature. The ions, on the other hand, undergo an irreversible temperature change of only 3."
Date: February 19, 1957
Creator: Colgate, Stirling A.
System: The UNT Digital Library
Preliminary Results of the Ratio of PU²³⁹ Fission Cross Section to U²³⁵ Fission Cross Section (open access)

Preliminary Results of the Ratio of PU²³⁹ Fission Cross Section to U²³⁵ Fission Cross Section

This report presents the final results from the investigation of the ratio of Pu-239 fission cross section to U-235 fission cross section. Three sets of plutonium and uranium foils were prepared at KAPL and were investigated to acquire the final results.
Date: February 20, 1953
Creator: Leonard, B. R.
System: The UNT Digital Library
Hanford Works Analytical Manual for Reactor Process Water (open access)

Hanford Works Analytical Manual for Reactor Process Water

Purpose: "The Hanford Works Analytical Manual for Process Water is designed to specify the analytical methods to be applied for control purposes in the Reactor Section, Process Sub-Section laboratories. The procedures are in general form and serve as references rather than outlined laboratory instructions. The manual us designed to replace the "Hanford Works Manual," HW-12862."
Date: February 13, 1953
Creator: Hanford Works
System: The UNT Digital Library