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Alloy Chemistry of Transition Elements
Alloy chemistry is the focus of this research paper with the study of the intermediate phases in ally systems.
Date:
March 30, 1962
Creator:
Nevitt, M. V.
System:
The UNT Digital Library
Analysis for Pu(III) and Pu(IV) on a Tracer Scale
A tracer scale analysis of the type of the zirconium phenylarsonate procedure is applicable to many types of solutions of plutonium which can not be analyzed spectrophotometrically and for that reason is very important.
Date:
December 1, 1944
Creator:
King, E. L.
System:
The UNT Digital Library
The Assembly: Sodium Bonding and Inspection of EBR-II Blanket Rods
The Experimental Power Breeder Reactor, EBR-II, is a heterogeneous, unmoderated, sodium cooled reactor to provide engineering and operational information applicable to full scale central-station nuclear power plants.
Date:
December 1960
Creator:
Salley, R. L. & Bean, C. N.
System:
The UNT Digital Library
Comments on "Application of Fluidization to Nuclear Technology"
The technique of solid fluidization has recently applied to the thermal conversion of uranyl nitrate into uranium trioxide. Two tests have been used to report the reactivity of uranium trioxide.
Date:
April 4, 1956
Creator:
Chu, Ju-chin
System:
The UNT Digital Library
The Corrosion of 1100 Aluminum in Oxygen Saturated Water at 70° C
In oxygen-saturated distilled water at 70°, the rate and amount of corrosion during short exposure are influenced by experimental conditions. One noteworthy effect is that contamination of the water by the reaction increases the corrosion rate.
Date:
August 23, 1962
Creator:
Draley, J. E.; Mori, Shiro & Loess, R. E.
System:
The UNT Digital Library
Development of Zirconium Clad Uranium Plates for Reactor Fuel
In this investigation a method has been developed for production of Zrclad uranium plate based upon previous investigations at Argonne and Oak Ridge National Laboratories, and preliminary in investigations in their present work. The present preliminary investigations included experimental studies of the effect of interface atmosphere upon roll bonding and led to the conclusion that thin layers of air between bonding surfaces could be tolerated.
Date:
May 6, 1953
Creator:
Lawless, J. J.; Bean, C. H.; Wooland, J. R. & Macherey, R. E.
System:
The UNT Digital Library
The Diffusion of Iron and Chromium in Beta Uranium
This note presents the results of some measurements of the diffusion of iron and chromium in beta uranium carried out in connection with studies of the diffusion of these tracers in gamma uranium
Date:
May 1, 1962
Creator:
Rothman, S. J. (Steven J.); Peterson, N. L. & Moore, S. A.
System:
The UNT Digital Library
Dislocation Etch Pits in Cu-A1 and Cu-Zn Alloys
This paper investigates whether or not dislocation etch pits can be developed in various Cu solid solutions using the same ideas developed by Young and Livingston.
Date:
August 13, 1962
Creator:
Koppenaal, Theodore J.
System:
The UNT Digital Library
Dissolution of Thorium Oxide-Uranium Oxide Fuel Elements
A promising new fuel element consists of urania in a thoria matrix is discussed.
Date:
August 9, 1956
Creator:
Larsen, R. P.
System:
The UNT Digital Library
Drawing of Tubes filled with Particulate Solids
The principal parameters involved in drawing of tubes filled with metallic, mineral and organic powders were investigated on small copper, mild steel and 304 stainless tubing.
Date:
December 31, 1962
Creator:
Polakowski, N. H. & Mayfield, R. M.
System:
The UNT Digital Library
Effect of Processing Losses on Breeding Gain and Doubling (Converting) Time for EBR-II and PBR Reactors
Due to interest in the break-even point at which losses in the overall fuel cycle neutralize the breeding gain, the effect of losses on doubling (converting) time has also been calculated in this study.
Date:
May 8, 1956
Creator:
Dillon, I. G.
System:
The UNT Digital Library
Effects of Oxygen and Surface Treatment on the Corrosion of Stainless Steel in Superheated Steam
Exploratory corrosion tests performed with stainless steels in steam at 650°C, 600 psi suggested a sharp dependence of corrosion behavior on surface treatment of the samples.
Date:
August 1962
Creator:
Greenberg, S. & Ruther, W. E.
System:
The UNT Digital Library
Electrodepostion of Plutonium from Molten Salt Solutions of Cs2PuCl6
The usefulness of molten salt solutions of Cs2PuCl6 for plutonium electrolyzes has been investigated. This work has shown that Pu metal can be electrodeposited from solutions of Cs2PuCl6
Date:
November 30, 1961
Creator:
Brodsky, M. B. & Carleson, G. F.
System:
The UNT Digital Library
An Electrolytic Process for Refining Commercial Uranium
Commercially available uranium metal containing significant amounts of iron, copper, chromium, manganese, nickel and silicon may be electrolytically refined to near spectroscopic purity.
Date:
August 2, 1953
Creator:
Noland, Robert & Marzano, Christopher
System:
The UNT Digital Library
Evaluation and Assembly by Vacuum Brazing of the Superheater Fuel Plates for the Boiling Reactor Experiment-V
The requirements for the Superheat fuel for BORAX-V necessitated developing special nondestructive methods for evaluating the fuel plate quality and a special technique for vacuum brazing the plates into rigid elements.
Date:
February 23, 1961
Creator:
Kramer, W. C. & Bean, C. H.
System:
The UNT Digital Library
An Evaluation of a Fast, Scintillator-Polaroid Film Camera for Neutron Image Detection
A new Polaroid camera for detecting thermal neutron images has been subjected to a series of tests to determine its usefulness for neutron radiography.
Date:
April 1962
Creator:
Berger, Harold & Kraska, I. R.
System:
The UNT Digital Library
Fabrication and Properties of US and Ths Bodies
The nuclear fuels field has shown increasing interest in compounds such as the carbides, nitrides, silicides and sulfides of uranium which give promise of semi-metallic properties in combination with refractoriness.
Date:
June 12, 1962
Creator:
Shalek, P. D.
System:
The UNT Digital Library
The Fabrication of the Fuel Elements for the Transient Reactor Test
The Transient Reactor Test Facility was designed and constructed to operate with a large trasient thermal flux for brief time intervals in order to permit meltown studies on mockups of fast ractor fuel elements and for certain other reactor safety studies.
Date:
June 1959
Creator:
Bean, C. N.; McCuaig, F. D. & Handwerk, J. H.
System:
The UNT Digital Library
A Film Copying Technique for Improving Radiographic Contrast
By copying radiographs on high gamma photographic film, a significant increase in overall system gamma can be obtained.
Date:
April 1962
Creator:
Beyer, N. S.; Berger, Harold; Lapinski, N. P. & Kraska, I. R.
System:
The UNT Digital Library
t'he Melting of High Purity Uranium
A melting process was developed by which high purity electrolytic uranium crystals can be converted into sound ingots without serious contamination.
Date:
November 14, 1952
Creator:
Blumenthal, B.
System:
The UNT Digital Library
An Induction Heated High Temperature X-Ray Diffraction Camera
A high temperature X-ray diffraction camera is described in which the sample is heated indirectly by induction in a vacuum or atmospher.
Date:
October 22, 1952
Creator:
Mueller, Melvin H. & Zauberis, Daniel D.
System:
The UNT Digital Library
Initial Superconductor Experiments
The purpose of this note is to summarize superconducting experiments as an aid to future superconducting investigations
Date:
August 10, 1962
Creator:
Fields, T. H.
System:
The UNT Digital Library
Kinetics. Experiment 27
This study was done to obtain information pertaining to the delayed photoneutrons and their effect on the reactor shutdown.
Date:
March 23, 1953
Creator:
Armstrong, J. & Olliff, W.
System:
The UNT Digital Library
Literature Search on Chemical Reduction of Uranium Oxides
Reduction of the oxide formed in the slagging operation has been suggested as a possible means of increasing the overall ingot recovery. The various reduction methods which have been investigated are reduction with calcium, magnesium, and carbon. Details of each method are discussed in this paper.
Date:
August 23, 1956
Creator:
Bennett, G. A.
System:
The UNT Digital Library