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A New Anionic Solvent Extraction Technique (open access)

A New Anionic Solvent Extraction Technique

From abstract: "The extraction of acids with long-chain amines is described. Preliminary results on the extraction of the amine salts of polonium, plutonium and uranium are given."
Date: July 17, 1952
Creator: Moore, F. L.; Kelley, M. T. & Susano, C. D.
System: The UNT Digital Library
Analysis of Bulk Shielding Facility Neutron Dosimeter Data (open access)

Analysis of Bulk Shielding Facility Neutron Dosimeter Data

Technical report calculating "effective removal cross sections" for Pb, Fe and O from measurements of fast neutron does in the water surrounding the BSF reactor. The values for Pb and Fe agree quite well with those previously determined from Lid tank data, whereas that for O is somewhat lower. [From Abstract]
Date: July 17, 1952
Creator: Podgor, S.
System: The UNT Digital Library
A Cement Base for the Hot Filament Mass Spectrometer Source (open access)

A Cement Base for the Hot Filament Mass Spectrometer Source

The following document is meant to inform the reader on the makings of a cement base for the hot filament mass spectrometer source as part of a publication in the review of scientific instruments, "Laboratory and Shop Notes".
Date: January 17, 1952
Creator: Hand, John E.
System: The UNT Digital Library
Studies of the Solvent Extraction Behavior of the Transition Elements: 1. Fractionation of the Trivalent Rare Earths (open access)

Studies of the Solvent Extraction Behavior of the Transition Elements: 1. Fractionation of the Trivalent Rare Earths

Report discussing the fractionation study of tri-n-butyl orthophosphate as the organic phase using a solution of trivalent rare earth chlorides or nitrates as the aqueous phase.
Date: January 17, 1952
Creator: Peppard, D. F.; Faris, J. P.; Gray, P. R. & Mason, G. W.
System: The UNT Digital Library
Some Effects of Irradiation on Metals (open access)

Some Effects of Irradiation on Metals

Report discussing several experiments investigating the effect of radiation on metals, specifically on intermetallic diffusion, mechanical properties of 347 stainless steel and electric resistance of 347 stainless steel.
Date: 1952-03-17?
Creator: Parkins, W. E.
System: The UNT Digital Library
Hydrogen Peroxide Analysis and Decomposition in Chromate Solutions (open access)

Hydrogen Peroxide Analysis and Decomposition in Chromate Solutions

Abstract: "A novel procedure employing ion exchange resins was developed to separate chromate ions from hydrogen peroxide, permitting, permitting the subsequent analysis of peroxide to determine its decomposition in sodium chromate solutions. At high pH's, peroxide was absorbed anionically on the ion exchange resins along with chromate. By selecting a resin which would be effective at nearly neutral conditions, chromate was satisfactorily separated from peroxide. It was found that the rate of peroxide decomposition in slightly alkaline sodium chromate solutions was dependent on temperature, pH, aeration, and chromate concentration. No significant effect on decomposition was caused by visible light."
Date: March 17, 1952
Creator: Rynasiewicz, Joseph & Ryan, J. W.
System: The UNT Digital Library
Zrclad Zirconium-Uranium Alloy Rod for Heat Thru-Put Test (open access)

Zrclad Zirconium-Uranium Alloy Rod for Heat Thru-Put Test

The purpose of this work was (1) to investigate the possibility of producing zirconium-clad zirconium-uranium alloy objects by casting the core alloy directly into zirconium and zirconium-3 w/o tin jackets, producing a diffusion bond at the jacket-core interfaces, and (2) to produce small scale heat thru-put test specimens by this method.
Date: April 17, 1952
Creator: Shuck, Arthur B., 1918-
System: The UNT Digital Library
The Manufacture of Aluminum Clad Aluminum-Plutonium Alloy Irradiation Specimens (open access)

The Manufacture of Aluminum Clad Aluminum-Plutonium Alloy Irradiation Specimens

This report describes the manufacture of 25 Aluminum clad, 10 w/o plutonium-aluminum alloy and 5 w/o plutonium-aluminum alloy cored specimens for Argonne National Laboratory-University of California irradiation tests in the Materials Testing Reactor. The manufacturing method: preparation of cores and cladding material, assembly and welding of compacts, outgassing, roll bonding, shearing, identification marking and final fabrication into napkin "rings" is described in detail. Of ninety-six specimens fabricated, ninety-one were completed as finished specimens. Forty-four of these contained 5 w/o plutonium alloy cores and forty-seven contained 10 w/o plutonium alloy cores. Five specimens ere rejected for bond blistering.
Date: April 17, 1952
Creator: Shuck, Arthur B., 1918-
System: The UNT Digital Library
Preliminary Studies for the Separation of HD from H2 by Rectified Absorption (open access)

Preliminary Studies for the Separation of HD from H2 by Rectified Absorption

The feasibility of rectified absorption for the recovery and purification of HD from H2 streams has been investigated. The absorbent considered was liquid nitrogen at 78 (degrees) K. The process appears to present no major engineering or operation problems. Cost calculations indicate that the process may be economically competitive with other processes. Process design was based on an estimated separation factor of 1.25 between H2 and HD in this system. Experimental work has been undertaken to check the validity of this estimate and to investigate the possibility of using other absorbents such as hydrocarbons and fluorocarbons.
Date: March 17, 1952
Creator: Hanson, Donald N.; Hunt, C. d'A.; Cook, M. W. & Fick, J. L.
System: The UNT Digital Library
Plastic Bonded RDX (open access)

Plastic Bonded RDX

This technical report describes the preparation and properties of plastic bonded RDX mixtures containing approximately 30 weight percent RDX. These mixtures may readily be prepared by a method adaptable to existing ordnance plant equipment. they are roughly comparable to Compositions A and B in sensitivity and explosive performance, but are much stranger physically than these or similar explosives.
Date: July 17, 1952
Creator: James, E. & Smith, L. C.
System: The UNT Digital Library
MTA, A-12 Development, Drift Tubes - RF and Beam Geometry. Comparison of A-12 to A-24 (open access)

MTA, A-12 Development, Drift Tubes - RF and Beam Geometry. Comparison of A-12 to A-24

The final r.f. characteristics of A-12 are shown. The mechanical features are available in UCRL-1859. If A-12 were to be changed to 24.2 mm rather than 12.1 mm, keeping the same length and the same constant average coil gradient of 0.375 MV/ft., the characteristics of such an A-24 can be obtained from the attached curves.
Date: November 17, 1952
Creator: Schelberg, A. & Kitchen, S.
System: The UNT Digital Library