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Twin Argon Welding of Alsi-Bonded Aluminum Clad Uranium Metal Fuel Elements
In the continuing search for better methods of effecting the secondary fusion welded closure in Alsi bonded aluminum clad uranium metal fuel element, an article on "The Twin-Argon Welding Process" by J. A. Donellon was recently found in the September 1954 issue if the British Welding Journal. From a review of the article, the process appeared to have enough possibilities to warrant exploring it. Communication were established with the General Electric Company, Ltd..
Date:
May 6, 1960
Creator:
Correy, Thomas B.
Object Type:
Report
System:
The UNT Digital Library
EGCR Lattice Radial and Angular Power Distribution 2.6 w/o Enrichment
The measurements reported here are companion measurements to those reported earlier in HW-63585. The only significant difference between the measurements is that 1.8 w/o enrichment UO2 fuel was used for the first set, and 2.6 w/o enrichment UO2 fuel was used for the measurements described in this report. The new results will be presented graphically, and for completeness, the details of the measurement will be included here as well as in HW-63585.
Date:
May 10, 1960
Creator:
Nichols, P. F.
Object Type:
Report
System:
The UNT Digital Library
Aluminum Alloy Work at Hanford
Investigation of aqueous and steam corrosion at elevated temperature has been carried on at Hanford for several tears. A number of reports have been published on various phases of the corrosion program but, except for monthly reports, little has been written on the progress of the Corrosion and Coatings Operation alloy development program. This interim report will outline the more important current phases of the aluminum alloy program.
Date:
May 6, 1960
Creator:
Bowen, H. C.
Object Type:
Report
System:
The UNT Digital Library
Unclassified Research and Development Programs Executed for the Division of Reactor Development and the Division of Research April 1960
A 19-rod Zircaloy-clad half-length PRTR spike element successfully irradiated to high plutonium burnout at full power in the ETR shoved partial bonding of the core and cladding. Unsatisfactory autoclave films on the Zircaloy cladding of the PRTR Al-Pu fuel elements are delaying final assembly of the first 30 clusters. Further conditioning of the autoclaves and the availability of permanent etching facilities are expected to correct the present difficulties.
Date:
May 10, 1960
Creator:
Hanford Laboratories Operation Irradiation Procesing Department
Object Type:
Report
System:
The UNT Digital Library
L/R Indicator
The evaluation of the inductance of an electrical component is often important in understanding and operating an electrical circuit. Inductance is defined by several equations, the most common being e= -L d1/dt . This equation defines inductance as the constant which relates the back emf produced in an element to the time-rate-of-change of current.
Date:
May 20, 1960
Creator:
Minor, G. C.
Object Type:
Report
System:
The UNT Digital Library
Plutonium Oxide- Plastic Mixtures for Critical Mass Studies
Critical mass experiments to be conducted at HAPO will require dilute and concentrated plutonium solutions. Since very high plutonium concentrations (~2,000 g/l) cannot be attained in pumpable solutions, solid plutonium compounds will be utilized for this phase of the work. Mixtures of plutonium oxide and polyethylene, methyl methacrylate or paraffin compacted in containers have been considers for use in highly-concentrated plutonium systems of known hydrogen to plutonium atomic ratio (H/Pu).
Date:
May 12, 1960
Creator:
Crocker, H. W.
Object Type:
Report
System:
The UNT Digital Library
Quarterly Report Technology of Non-Production Reactor Fuels Processing Budget Activity 2790
This report summarizes the research and development work carried out during December, 1959, and January and February, 1960, for Budget Activity 2790 - Separations Development for Non-Production Reactors. The major effort on Activity 2790 has been completed. Current efforts on the remaining problem areas will enable Hanford to begin reprocessing fuel elements from power reactors which employ depleted or slightly enriched uranium fuels in July, 1962.
Date:
May 19, 1960
Creator:
Cooper, V. R.
Object Type:
Report
System:
The UNT Digital Library
Nuclearly Safe Mass Limits, Volume Limits, Infinite Cylinder Diameters and Slab Thicknesses for Slightly Enriched Uranium Rods in Light Water
Graphs have been made which show the nuclearly safe parameters for uranium rods in light water with uranium enrichments up to five weight percent U-235. These data were to serve as a guide to those persons who may be involved with the maintenance of nuclear safety in handling and processing operations with slightly enriched uranium fuel elements. The data are applicable to fuel element fabrication and processing operations, and in general to those operations involving the handling and storage of fuel elements apart from reactors.
Date:
May 24, 1960
Creator:
Clayton, E.D.
Object Type:
Report
System:
The UNT Digital Library
Synchrotron Oscillations
Some numerical calculations have been done which permit the deduction of many properties of the synchrotron oscillation problem. For the presentation of the numerical results, it is useful to review the formulation framework to which the results are to be fitted. These are worked out for an arbitrary circular accelerator. The algebra woud have to be modified slightly to include straight sections but the numerical results are still useful.
Date:
May 1, 1962
Creator:
Hochman, E. H. & Barton, M. Q.
Object Type:
Report
System:
The UNT Digital Library
The Ball Tuner Change Tables
Technique used in deriving values of the linac ball tuner settings to produce various fields is discussed briefly, and tables showing ball tuner change numbers and values used in making up the ball tuner change numbers are given.
Date:
May 3, 1962
Creator:
Walters, J. L.
Object Type:
Report
System:
The UNT Digital Library
Design of Reflectometers for Coaxial Lines Used at AGS LINAC
This report describes the design procedure for a reflectometer or directional coupler to replace the probe part of the D07-1020 assembly used at the Brookhaven Alternating Gradient Synchrotron linac. Mathematical treatment and diagrams of various reflectometers are included.
Date:
May 9, 1962
Creator:
Walters, J. L.
Object Type:
Report
System:
The UNT Digital Library
Some Properties of Stub Tuners Which Can Be Displayed On Smith Charts
Use of the Smith chart in studying stub tuners is demonstrated. Several properties of the tuners are shown, and charts for various wave length spacings, tuning trajectories, and admittances are included.
Date:
May 9, 1962
Creator:
Walters, J. L.
Object Type:
Report
System:
The UNT Digital Library
Chemical Separation of Isotopes Section Semiannual Progress Report For Period Ending December 31, 1954
New systems involving the exchange of boron between boron trifluoride and boron trifluoride addition compounds have been explored. These systems have large separation factors and potentially simple reflux mechanisms. A precise determination of this separation factor for the anisole-boron trifluoride system gave the value (see report). Boron exchange was found to occur between BF and BCl3. Several homogenous catalysts have been found which activate the hydrogen-water exchange, but none are adoptable to the production of deuterium because of the slow exchange rate. Platinum or platinum oxide may be usable as a heterogeneous catalyst with proper support or dispersion techniques. The high-pressure solubility of hydrogen in several amalgams was investigated in connection with a unique countercurrent exchange system. A proposed system involving isotopic exchange between lithium dipivaloylmethane in diethyl ether and lithium hydroxide in aqueous solution was shown to give little or no isotopic separation. Column studies of the carbonate system exchange reaction were concluded with a 40°C run. Slightly higher enrichment of N15 was obtained than at 30°C . The temperature dependence of all in this system was measured between 15 and 45°C. The factor increases with temperature, showing a tendency toward a maximum near 45°C. Isotopic exchange appears to …
Date:
May 20, 1955
Creator:
Clewett, G. H & Drury, J. S.
Object Type:
Report
System:
The UNT Digital Library
Analytical Chemistry Division Semiannual Progress Report For Period Ending April 20,1955
The development of ionic methods for the determination of corrosion products in the highly radioactive Homogeneous Reactor (HR) fuels has been of major interest in the work of the Ionic Analyses Laboratory. Methods for the spectrophotometric determination of aluminum and for the polarographic determination of iron in HR fuels have been developed. The polarographic determination of molybdenum in uranyl sulfate solutions was studied. A polarographic method for the determination of zinc was developed. A fluorometric method for the determination of microgram amounts of fluoride was studied. Three organic reagents were investigated as precipitants for microgram quantities of zirconium in HR fuel. The automatic photometric titration technique was applied to the determination of thorium and of sulfate. A method was developed for the ionexchange separation and potentiometric titration of cobalt. The ultraviolet absorption spectra of technetium and rhenium were studied.
Date:
May 6, 1955
Creator:
Kelley, M. T.; Susano, C. D. & Raaen, H. P.
Object Type:
Report
System:
The UNT Digital Library
The Extraction and Recovery of Uranium (and Vanadium) from Acidic Liquors with DI (2-Ethylhexyl) Phosphoric Acid and Some Other Organophosphorus Acids
Bench scale studies have been made of the recovery of uranium from acid leach liquors (and slurries) by solvent extracting with di (2-ethylhexyl) phosphoric acid in an organic diluent. Uranium may be stripped from the organic solvent by either alkaline or acidic reagents, the former having been studied in greater detail. On the basis of these tests, a recovery process may be considered which shows promise both from the standpoint of operation and chemical costs. Under proper conditions, vanadium can also be extracted by the di (2-ethylhexyl) phosphoric acid and stripping again may be accomplished with either acidic or alkaline reagents. Preliminary studies have been made of these possibilities. In addition to di (2-ethylhexyl) phosphoric acid, some other organophosphorus acids, have been cursorily examined in respect to their extraction and/or stripping performance.
Date:
May 13, 1955
Creator:
Blake, C. A.; Brown, K. B.; Coleman, C. F.; Horner, D. E. & Schmitt, J. M.
Object Type:
Report
System:
The UNT Digital Library
Interim Evaluation of the Fluorox Process for UF4 and UF6 Manufacture
The conversion of UNH to UF4 and UF6, utilizing moving-bed techniques, is being studied; sufficient progress has been made that an evaluation of the process is warranted. The procedures under study, the Fluorox Process, have three major advantages: (1) substitution of HF for high-cost fluorine, (2) considerable reduction in HF requirements, and (3) marked reduction in plant-size and mechanical complexity.
Date:
May 26, 1955
Creator:
Moore, J. E.
Object Type:
Report
System:
The UNT Digital Library
A Combined Distillation-Electrochemical Method for Recovery of Hydrofluoric Acid
Electrodialysis in an ion-exchange membrane cell was shown to be technically feasible for the concentration of an azeotropic mixture of HF and water. A flowsheet is presented for recovery of anhydrous HF by distillation and electrodialysis of the azeotropic residue. In the electrodialysis step, 2.6 kwhr of energy per pound of anhydrous product was consumed, with electricity at 1¢ per kilowatt-hour, the total operating cost of the electrodialysis equipment alone, including amortization, would be 6¢ per pound of HF.
Date:
May 25, 1956
Creator:
Marinsky, J. A. & Giuffrida, A. J.
Object Type:
Report
System:
The UNT Digital Library
Bulk ThO2, a Reactor Material
Thorium, a fertile material, is of interest to the Reactor Program in the production of U233. Thorium can be extracted and processed to a very pure bulk metal for fabrication into solid fertile elements. There are advantages, technical and economic, for using fabricated bulk thorium dioxide rather than the metal in some applications. It is the purpose of this paper to point out these advantages and to present briefly the technology related to fabrication, radiation damage and chemical processing of ThO2.
Date:
May 24, 1956
Creator:
Johnson, J. R. & Warde, J. M.
Object Type:
Report
System:
The UNT Digital Library
Thorex Thorium Nitrate Product Specifications
Activity and ionic impurity specifications are presented for Thorex thorium nitrate products. Two sets of specifications are given, one set for direct handling during refabrication of production reactor thorium metal slugs and the second for refabrication of future power reactor thorium metal elements by semi-remote technics. Consideration was given to the health hazard problems associated with each process step between the Thorex process and final refabricated source material in order to arrive at these specifications.
Date:
May 24, 1956
Creator:
Arnold, E. D. & Wischow, R. P.
Object Type:
Report
System:
The UNT Digital Library
The ANCO System for Boron Isotope Enrichment Progress Report for Period Ending September 20, 1955
A new gas-liquid countercurrent system (the ANCO system from Anisole-Complex) for the enrichment of boron isotopes has been developed. It is believed that use of this systems will result in a considerably lower unit cost for enriched boron-10 than was previously possible. The system utilizes the exchange reaction between BF3 (gas) and BF3·anisole (liquid) to concentrate boron-10 in the liquid phase. The single stage isotopic separation factor for this system has been found to vary from 1.039 at 0°C to 1.029 at 30°C. The isotopic exchange reaction has been shown to be rapid. Vapor pressures of the complex as a function of temperature have been measured and the heat of formation of the complex determined. Laboratory experiments show that quantitative removal of the BF3 from the complex can be accomplished by heating. A complete miniature ANCO plant was constructed and operated in the laboratory to test the feasibility of the system. The system was found to operate efficiently with a minimum of attention, and to enrich the isotopes of boron as expected. Based upon the experience obtained with the laboratory ANCO unit, a pilot plant large enough to utilize a 6-inch diameter exchange column was designed. The design calculations of …
Date:
May 1, 1956
Creator:
Healy, R. M.; Joseph, K. F. & Palko, A. A.
Object Type:
Report
System:
The UNT Digital Library
Railroad Commission of Texas Strategic Plan: Fiscal Years 2021-2025
Agency strategic plan for the Railroad Commission of Texas describing the organization's planned services, activities, and other goals during fiscal years 2021 through 2025.
Date:
May 20, 2020
Creator:
Railroad Commission of Texas
Object Type:
Report
System:
The Portal to Texas History
Plutonium-Metal Critical Assemblies
The two plutonium-metal critical assemblies that have been studied at Pajarito Site are Jezebel, bare plutonium; and Popsy, a plutonium core in a thick normal uranium reflector. These assemblies and their properties are described.
Date:
May 1956
Creator:
Jarvis, G. A.; Linenberger, G. A. & Paxton, Hugh Campbell
Object Type:
Report
System:
The UNT Digital Library
Welding of Plutonium
Delta-stabilized plutonium can be welded to itself or almost any other metal using the inert-gas metal-arc process. Equipment and procedures suitable for the welding of delta-stabilized plutonium under various conditions are described.
Date:
May 9, 1958
Creator:
Anderson, J. W.
Object Type:
Report
System:
The UNT Digital Library
Possible Substitutes For Glue in South African Ore Treatment
We investigate the possibilities of using another reagent than glue as a filtration aid in South African ore treatment.
Date:
May 14, 1951
Creator:
Woody, R. J.
Object Type:
Report
System:
The UNT Digital Library