Effect of Solvent Degradation on the Purex Process (open access)

Effect of Solvent Degradation on the Purex Process

From abstract: "The combined attack of HNO3 and HNO2 on tributyl phosphate - kerosene solvent used in the Purex process produces degradation products that cause abnormal quantities of zirconium to be extracted along with the plutonium and uranium and thus limits the decontamination."
Date: May 1958
Creator: Siddall, Thomas H., III; Wallace, Richard M. & Prout, W. E.
Object Type: Report
System: The UNT Digital Library
Effect of Temperature and Reactivity Changes in Operation of the Los Alamos Plutonium Reactor (open access)

Effect of Temperature and Reactivity Changes in Operation of the Los Alamos Plutonium Reactor

The operation of the Fast Reactor is considered in terms of normal equilibrium conditions and normal shut-down. The proposed loading, control rod adjustment and subsequent "floating" operation are discussed. Safety devices and interlocks are described. Temperature and reactivity changes are examined with respect to various system failures, phase changes, and "flashing" of the reactor. Slow changes due to faulty slug cooling are also considered. The calculations were initially based upon 10 kw operation. Performance tests of the mercury system now indicate that 20-kw operation may be feasible.
Date: May 28, 1948
Creator: Hall, David B. & Hall, Jane H.
Object Type: Report
System: The UNT Digital Library
Effects of Letdown Rates and Oxygen Injection Rates on Xenon Poison Level and Excess Oxygen Concentration in the HRT (open access)

Effects of Letdown Rates and Oxygen Injection Rates on Xenon Poison Level and Excess Oxygen Concentration in the HRT

Calculations indicate that it is impossible, even at high oxygen injection rates, to insure an excess of oxygen in the HRT fuel solution if the bubble letdown rate is more than 1 or 2 liters per minute. If, on the other hand, no bubbles are allowed to form, a reasonable excess oxygen concentration can be maintained with an oxygen injection rate which would not tax the capacity of the off-gas system. The xenon poison will be reduced to less than 2% by liquid letdown alone, and if an iodine absorption bed is installed below the catalytic recombiner, the xenon poison should be less than 1% without any bubble letdown. Therefore, it is recommended that sufficient copper be added to prevent the formation of gas bubbles and that the oxygen injection rate be limited to a value which would permit adequate holdup times in the present charcoal adsorption beds, assuming this quantity is sufficient to meet corrosion requirements.
Date: May 31, 1957
Creator: Haubenreich, P. N.
Object Type: Report
System: The UNT Digital Library
Effects of Receiver Slots on Quantity and Quality of Product and Recycle (open access)

Effects of Receiver Slots on Quantity and Quality of Product and Recycle

Abstract: "Variations in receiver slot design produce changes in quantity and quality of product and recycle, not only instantaneously, but also as a function of time in approaching equilibrium. The case of fixed feed concentration and fixed inventory of Uranium is described here for standard and Dip-Lip wider R slot receivers. The effects of the two types of receivers on recycle and product X and W concentrations, X production rate, plant X utilization efficiency, integrated X production and effective mass output are shown graphically."
Date: May 29, 1947
Creator: Harmatz, Benjamin
Object Type: Report
System: The UNT Digital Library
EGCR Lattice Radial and Angular Power Distribution 2.6 w/o Enrichment (open access)

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
Electrolytic Reduction of Uranyl Ion (open access)

Electrolytic Reduction of Uranyl Ion

From introduction: "Due to the hydrogen overvoltage at the surface of a mercury cathode, uranium solutions is hydrochloric acid may be reduced not only to the tetravalent state, but until considerable trivalent uranium is formed. Other metallic ions act as oxidation-reduction catalysts as well as being reduced themselves. The following paper is a study of the various reactions taking place in solution and at the surface of the cathode."
Date: May 27, 1946
Creator: Nichols, Ambrose R., Jr.
Object Type: Report
System: The UNT Digital Library
Electron-Electron Coincidence Spectrometer BRS-IV (open access)

Electron-Electron Coincidence Spectrometer BRS-IV

This report summarizes the original construction and recent modifications of the electron-electron coincidence spectrometer BRS-IV located in Building 70 of the Lawrence Radiation Laboratory. In addition to new information on the modified spectrometer, this report also contains a large amount of material taken from two previous UCRL reports.
Date: May 1960
Creator: Unik, John P.
Object Type: Report
System: The UNT Digital Library
Electron Microscope Studies of Irradiated Beryllium Metal (open access)

Electron Microscope Studies of Irradiated Beryllium Metal

When beryllium is irradiated by fast neutrons, helium is produced by the (n,2n) and (n,α) transmutation reactions. Electron microscopy techniques have been used to study the nucleation and distribution of helium bubbles in several different grades of beryllium, after irradiation at temperatures in the range 75 — 700ºC. The effect of post-irradiation annealing is also reported. It is shown that for similar neutron doses and irradiation temperatures, there were wide variations in helium bubble size and distribution in specimens of beryllium fabricated by different methods. The most satisfactory material was that fabricated from Pechiney powder by direct hot extrusion followed by annealing for one hour at 800ºC and air cooling, it is suggested that the helium bubbles nucleate on second phase precipitates and that the distribution of this phase is strongly affected by fabrication and heat treatment.
Date: May 1963
Creator: Chute, J. H.
Object Type: Report
System: The UNT Digital Library
Electron Requirements of Bonds in Metal Borides (open access)

Electron Requirements of Bonds in Metal Borides

From abstract: "Electrical measurements have been made on CaB6, SrB6, BaB6, YB2, YB4, YB6, and YB12 for the purpose of testing models of the electronic structure of the boron atoms in the four boride types represented. The compounds CaB6, SrB6, and BaB6 were found to be semiconductors. The Hall coefficients of YB4 was also measured, but could not be interpreted because the free electron theory does not provide a theoretical value for comparison with experiment. The results are in agreement with the models proposed."
Date: May 28, 1962
Creator: Johnson, Robert W. & Daane, A. H. (Adrian Hill), 1919-
Object Type: Report
System: The UNT Digital Library
Electron Spectrum of Pa²³³ (open access)

Electron Spectrum of Pa²³³

The following report describes the electron spectrum of protactinium derived from 23 minute thorium 233 that was produced by neutron capture in stable thorium.
Date: May 9, 1950
Creator: Keller, H. B. & Cork, James M.
Object Type: Report
System: The UNT Digital Library
Electroplated Metals on Uranium (open access)

Electroplated Metals on Uranium

The following report follows the studies of electroplating on uranium and concurrent metallurgical clodding.
Date: May 7, 1954
Creator: Beach, John G.; Schickner, W. C.; Konecny, C. R. & Faust, Charles L.
Object Type: Report
System: The UNT Digital Library
Electroplated Metals on Uranium for Aluminum Cladding (open access)

Electroplated Metals on Uranium for Aluminum Cladding

Abstract: "Aluminum-clad nickel-plated uranium is corrosion resistant in boiling water. Samples with intentional defects in the aluminum-nickel clodding layers, after testing for more than 300 hr. showed no sign of rapid failure. The study of electroplated metals on uranium for aluminum cladding has defined the effects of several processing variables on the corrosion resistance. The quality of the uranium and the quality of the aluminum-nickel bond were important. Heat treatment and vacuum outgassing of the nickel-plated uranium prior to aluminum cladding were beneficial, and minimizing the amount of air present in the hot-press assembly was desirable. Variation in the steps for electroplating on uranium did not affect the corrosion resistance of aluminum-clad uranium."
Date: May 4, 1955
Creator: Beach, John G.; Schickner, William C.; Hopkinson, Dolores. & Faust, Charles L.
Object Type: Report
System: The UNT Digital Library
Elementary Theory of Neutron Sources in Reactors (open access)

Elementary Theory of Neutron Sources in Reactors

The following report discusses neutron sources in reactors, discussing general conditions of the study using a flux reactor.
Date: May 18, 1951
Creator: Masket, Albert Victor Hugo, 1914-
Object Type: Report
System: The UNT Digital Library
Employment of the Spiral Orbit Spectrometer to Measure PIon Production Ratios by Proton Bombardment (open access)

Employment of the Spiral Orbit Spectrometer to Measure PIon Production Ratios by Proton Bombardment

Plus-minus ratios for pion production by 340-Mev proton bombardment were measured at 13 Mev, 18 Mev, and 42 Mev with the use of the spiral orbit spectrometer.
Date: May 26, 1953
Creator: Sagane, Ryokichi, 1905-1969
Object Type: Report
System: The UNT Digital Library
Energy Per Fission and Power of the Bulk Shielding Reactor (open access)

Energy Per Fission and Power of the Bulk Shielding Reactor

Due to some lack of knowledge of the energy per fission, there has been some uncertainty over the absolute power of the Bulk Shielding Reactor. This report analyzes measurements to state the absolute power of the BSR within a few percent.
Date: May 12, 1953
Creator: Meen, J. L.; Johnson, E. B. & Hungerford, H. E.
Object Type: Report
System: The UNT Digital Library
Engineering Properties of High-Density Concretes (open access)

Engineering Properties of High-Density Concretes

From summary: "Methods were developed for measuring various engineering properties of high-density concretes. Data are presented on selected thermal properties of a limonite-iron concrete and the mechanical properties of the limonite-iron concrete, a magnesium oxychloride concrete, and a Portland cement concrete containing steel punchings and shot (no limonite)."
Date: May 1951
Creator: Snyder, M. Jack; Burkart, C. A. & Clegg, John W.
Object Type: Report
System: The UNT Digital Library
The Equation of State of the Alkali Halides at High Pressure (Thesis) (open access)

The Equation of State of the Alkali Halides at High Pressure (Thesis)

The following report investigates the cohesive energy of ionic crystal lattices in the alkali halides when at a high pressure.
Date: May 16, 1957
Creator: Christian, Russell H.
Object Type: Report
System: The UNT Digital Library
Equation of State of Water (open access)

Equation of State of Water

A generalization of the Fermi-Thomas model for application of mixtures. This study attempts to determine the equation of state of water up to pressure of 10,000 megabars and temperatures of several thousand electron-volts.
Date: May 23, 1955
Creator: Latter, Albert L. & Latter, Richard
Object Type: Report
System: The UNT Digital Library
The Equation of the Fusion Curve (open access)

The Equation of the Fusion Curve

A generalization of the Lindemann law is used in connection with the Murnaghan equation of state for a solid to derive theoretically the empirical Simon equation for the fusion curve. For the alkali metals it is shown that experimental values of the temperature exponent in the Simon equation are quantitatively compatible with the theoretical evaluation given, and, furthermore, that the theory can predict approximate values of the experiment, in practice.
Date: May 24, 1955
Creator: Gilvarry, J. J. (John James), 1917-
Object Type: Report
System: The UNT Digital Library
Equilibrium Relationships for Stripping Uranium from Solutions of Tributyl Phosphate and Hydrocarbon Diluent (open access)

Equilibrium Relationships for Stripping Uranium from Solutions of Tributyl Phosphate and Hydrocarbon Diluent

Objective: "The laboratory equilibrium study RC-E-1 described in this report was carried out to obtain uranium equilibrium curves at various concentrations of nitric acid and of TBP."
Date: May 1, 1950
Creator: Clagett, Fred
Object Type: Report
System: The UNT Digital Library
Equipment and Preliminary Results for the Leaching of UO2 in a Basic Carbonate Circuit (open access)

Equipment and Preliminary Results for the Leaching of UO2 in a Basic Carbonate Circuit

Equipment has been designed and constructed for the purpose of leaching pure uranium minerals in both acidic and basic circuits. This equipment provides a means for removal of a series of samples during any one run, control over speed of agitation, indication of gas over pressure, and automatic temperature control. These units may be operated up to 1500 p.s.i. Solid UO2 samples were prepared by sintering under hydrogen to 1800 degree C. Preliminary results of the leaching of sintered UO2 in a basic Na2CO3-NaHCO3 circuit resulted in the formation of an insoluble yellow precipitate (probably Na2UO4) for low concentrations of Na2-NaHCO3. At higher carbonate concentrations no insoluble precipitate was formed and the rate of leaching was found to increase vary rapidly above 300 p.s.i. oxygen over pressure.
Date: May 1955
Creator: Pearson, Ray L.; Mackay, Theron L.; Wadsworth, Milton E. & Fassell, W. Martin, Jr.
Object Type: Report
System: The UNT Digital Library
Euorochemic Assistance: Chemical Technology Division Unit Operations Section Monthly Progress Report, November, 1958. (Sections 1.0, 5.0, 6.0, 8.0 of ORNL CF-58-11-93) (open access)

Euorochemic Assistance: Chemical Technology Division Unit Operations Section Monthly Progress Report, November, 1958. (Sections 1.0, 5.0, 6.0, 8.0 of ORNL CF-58-11-93)

To better understand the solvent extraction process much effort has been and is being expended at ORNL and elsewhere to measure reaction kinetics of the extraction reactions. To date these efforts have been largely unsuccessful, due to the attempt to apply homogeneous reaction kinetics to two-phase systems. An optical method has been devised for analyzing the concentration profile in the vicinity of a quiescent interface during steady-state diffusion at rather large molecular fluxes. The system under study is the extraction of uranyl ion from water by a TBP solution. Considerable effort has been directed to eliminating leaks in the diffusion cell and testing the optical system/
Date: May 1, 1959
Creator: Shank, E. M.
Object Type: Report
System: The UNT Digital Library
Eurochemic Assistance: Chemical Technology Division Unit Operations Section Progress Report, December, 1958. (Sections 5.0, 6.0, 8.0) (open access)

Eurochemic Assistance: Chemical Technology Division Unit Operations Section Progress Report, December, 1958. (Sections 5.0, 6.0, 8.0)

In order to make rational predictions of the operating characteristics of uranium anion exchange contactors, an understanding of the mechanism and kinetics of the exchange is necessary. Toward this objective an effort is being made to determine the equilibrium sorption isotherms and rates of sorption of uranium on the anion exchange resin Dovex 21K.
Date: May 1, 1959
Creator: Shank, E. M.
Object Type: Report
System: The UNT Digital Library
Eurochemic Assistance: Monthly Progress Report for Chemical Development Section B, January, 1959 (Sections 1.0, except 1.42, and 2.0) (open access)

Eurochemic Assistance: Monthly Progress Report for Chemical Development Section B, January, 1959 (Sections 1.0, except 1.42, and 2.0)

In order to make rational predictions of the operating characteristics of uranium anion exchange contactors, an understanding of the mechanism and kinetics of the exchange is necessary. Toward this objective an effort is being made to determine the equilibrium sorption isotherms and rates of sorption of uranium on the anion exchange resin Dovex 21K.
Date: May 1, 1959
Creator: Shank, E. M.
Object Type: Report
System: The UNT Digital Library