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Division of Reactor Development Programs Monthly Report- August 1959
Sinterability studies on mixtures of UO2 and PuO2 powders have been continued. All of the censities from previous sintering experiments have been recalculated utilizing a somewhat different water immersion technique. Since densities of pellete obtained by physical dimensions are inaccurate due to chipping, and water immersion does not account for the open porosity, the pellets were coated with clear krylon before being immersed in water. This effectively sealed the open pores. Plots of density versus composition still indicate a drastic reduction in UO2 sinterability with even the slightest additions of PuO2 and a rapid increase with PuO2 contents greater than 20 weight percent. The following table compares densities of pure UO2 and PuO2 after an eight hour soak time:
Date:
September 15, 1959
Creator:
McEwen, L.H.
Object Type:
Report
System:
The UNT Digital Library
PRTR High Pressure Loop Hazards Survey of Preliminary Scope Design
Conceptual design studies conducted at HAPO indicate that the improved thermal efficiencies which can be obtained in a high pressure, high temperature, nuclear-electric power plant might reduce unit power costs substantially. The Plutonium Recycle Test Reactor (PRTR) is designed primarily to investigate various facets of plutonium recycle operation. In order to increases the usefulness of the PRTR as an experimental tool, it is desirable to include facilities for testing materials and fuel concepts under a variety of conditions, including the high temperatures and pressures which may be encountered in future water-cooled power reactors.
Date:
October 15, 1959
Creator:
Walkup, P. C.
Object Type:
Report
System:
The UNT Digital Library
Comments on Engineering Review of PRTR by Atomic Power Equipment Department
On a project of the magnitude and complexity of the Plutonium Recycle Test Reactor is was considered prudent engineering practice to obtain an independant design review by a competent off-site group that had not participated in any way in the development of the design. Accordingly, the Atomic Power Equipment Department of the General Electric Company was requested to make such an engineering review, and an Assistance to Hanford contract authorizing this work was approved by the Atomic Energy Commission in November, 1958.
Date:
October 15, 1959
Creator:
Reactor and Fuels Researcg and Development Operation Hanford Laboratories Operation
Object Type:
Report
System:
The UNT Digital Library
Gamma Ray Polymerization of Acrylamide in the Solid State
The polymerization of vinyl monomers can be initiated by heat, ultraviolet radiation, and various catalysts. More recently, ionizing radiation has been shown to effectively initiate vinyl polymerization. However, polymerization in the solid state by ionizing radiation is not reported in the literature, although several papers have been published that describe briefly the thermal polymerization of divinyldiphenyl, Leuch's anhydride and in greater detail the peroxide catalyzed polymerization of acetaldehyde. The purpose of this note is to describe some experiments which demonstrate that crystalline acrylamide undergoes polymerization upon irradiation with γ-rays from an intense Co-60 source. Below its melting point the monomer shows little or no tendency to polymerize thermally.
Date:
January 15, 1954
Creator:
Mesrobian, Robert, B.; Ander, Paul; Ballantine, David, S. & Dienes, G. J.
Object Type:
Report
System:
The UNT Digital Library
LMFR Progress Letter for March 1954
Summary of miscellaneous updates related to the project. This includes information on the following: the declassification of a relevant paper, solubility measurements, static corrosion tests, various other tests involving bismuth, magnesium, uranium, protactinium, and thorium.
Date:
April 15, 1954
Creator:
Miles, F. T.
Object Type:
Report
System:
The UNT Digital Library
The Irradiated Rupture Prototype (IRP) Design
One of the problems involved in the design of NPR is the method to be used for decontamination, Considerable effort has been made in both laboratories and pilot plants in developing and evaluating decontamination processes under ideal conditions. Promising processes must be tested under prototypical conditions of velocity, water quality, manner of make-up, type and degree of contamination, addition of decontaminating solutions, and so on.
Date:
February 15, 1960
Creator:
Neibaur, G. E. & Stice, N. D.
Object Type:
Report
System:
The UNT Digital Library
Ionium (Thorium-230) for Radioisotope Preparation (Status Report)
For many years effort has been directed toward the development of means for the practical utilization of the heat evolved from the radioactive decay of certain fission and irradiation products. Fission products, in view of their availability in the plentiful, high-level wastes resulting from the processing of irradiated, nuclear reactor fuels have been most intensively studied for applications where their heat of decay might be converted into useful energy such as electricity for the operations of certain devices in place of chemical batteries . In addition other materials having desired radioactive properties may be produced by neutron bombardment of readily available elements.
Date:
December 15, 1959
Creator:
Coppinger, E. A. & Rohrmann, C. A.
Object Type:
Report
System:
The UNT Digital Library
Unique Fabrication Processes Applied to Fuel Cladding Materials
The fabrication processes applied to nuclear fuels are subject to severe limitations because of the conditions imposed by the reactor environment. The combined problems of neutrons fluxes, high heat fluxes, corrosion by the coolant , and embrittlement by hydriding or similar reactions may be minimized through establishing rigorous materials and fabrication specifications for fuel and cladding.
Date:
March 15, 1960
Creator:
Bush, S. H.
Object Type:
Report
System:
The UNT Digital Library
Problems of a Small Leak Between the Flow Monitor and Heated Section of a PRTR Process Tube
The result of a leak in a PRTR process tube between the flow monitor and the heated section would be to increase the flow through the monitor, but to decrease the flow through the heated section. The concern for the case of small leaks is whether the increase in flow through the flow monitor is sufficient to cause a high flow tip and a reactor scram for the condition where the flow through the heated section is reduced to the point to cause excessive fuel element temperatures.
Date:
March 15, 1960
Creator:
Hesson, G. M.
Object Type:
Report
System:
The UNT Digital Library
Water Chemistry for KER Loop 1- June 29, 1959 to December 31, 1959
One of the primary reasons for operating the high pressure KER loops is to obtain information concerning water quality control characteristics for recirculating water cooled reactors. The KER-1 loop is predominantly carbon steel and approximates the water quality conditions specified for the New Production Reactor (NPR).
Date:
June 15, 1960
Creator:
Demmitt, T. F. & Wood, E. R.
Object Type:
Report
System:
The UNT Digital Library
Sampling and Analytical Data on Al-Pu Alloy for PRTR Start-Up Tests
In answer to the question, "How well do we know the composition of the fuel material for the PRTR start-up tests?", the analytical data on the PRTR fuel elements and other fuel elements which were fabricated by similar processes was gathered and analyzed. The results of this analysis are presented.
Date:
June 15, 1960
Creator:
Bloomster, C. H.
Object Type:
Report
System:
The UNT Digital Library
Computations for AGS Experimental Beams: Description of Computer Program
Description of a computer program which optimizes the locations and strengths of magnets for experimental beams at the Brookhaven AGS written for the IBM 7090 computer. Layout, method, and routines are given particular attention, and representative data cards are shown.
Date:
December 15, 1961
Creator:
Baker, Winslow F.
Object Type:
Report
System:
The UNT Digital Library
Servo Stabilized RF Vernier Time-of-Flight Analyzer
The analyzer can be operated either internally or externally. The 10 ma germanium discriminator is quiescently biased to 8.5 ma in its low-voltage state. An input signal current of 3.5 ma or more triggers it to its high voltage state. This triggers the oscillator. The oscillator signal is buffered and mixed in the bridge modulator with the reference radiofrequency signal from the cyclotron. The low-frequency beat note from the bridge modulator is squared up and passed to the beat zero univibrator which generates 0.7 mu sec signals each time the beat note passes through zero from positive to negative. The trailing edge of the beat zero univibrator is employed to terminate the time-of-flight measurement and to control the servo measurement. Drawings are included. (M.C.G.)
Date:
January 15, 1962
Creator:
Chase, Robert L.
Object Type:
Report
System:
The UNT Digital Library
6 kv Capacitor Charging Supply
The power supplies designed and constructed to power high intensity flash tubes used in bubble chamber experiments are briefly described and are accompanied by a schematic diagram of the layout. (D.C.W.)
Date:
March 15, 1962
Creator:
Miller, D. M.
Object Type:
Report
System:
The UNT Digital Library
0-2 kv Flash Tube Supplies
In order to perform the various experiments with a bubble chamber, a high intensity flash tube is used. This report briefly describes the power supplies designed and constructed to power these lamps.
Date:
March 15, 1962
Creator:
Miller, D. M.
Object Type:
Report
System:
The UNT Digital Library
The Effect of Acidity and Reducing Agents on Ruthenium Solvent Extraction by Tributyl Phosphate in the 25 Process
Results of tracer studies suggest that, in tributyl phosphate extraction processes designed to recover and purify fissionable material, minimum ruthenium extraction should be obtained from feeds at least 2 M in nitric acid or at least 1 M acid-deficient. Ruthenium decontamination was decreased by preheating the feed and increased by pretreatment with reducing agents. A pretreatment using 0.06 M ferrous ion and 0.5 M urea with 1 hr simmering at 85°C should increase ruthenium decontamination about 10-fold in the 25 process. If other process considerations dictate the use of a low-acid feed, decontamination from ruthenium may be improved by using 3 M nitric acid as the scrubbing solution. Apparently, the scrubbing process is quite time-dependent; a solvent holdup time of about 15 min may be needed in the scrub section for maximum decontamination.
Date:
December 15, 1954
Creator:
Flanary, J. R. & Frashier, L. D.
Object Type:
Report
System:
The UNT Digital Library
Disassembly and Postoperative Examination of the Aircraft Reactor Experiment
The Aircraft Reactor Experiment (ARE)was successfully concluded in November of 1954, and a detailed report of the operation was published the following year. At that time it was thought that an extensive examination of the reactor and system components after disassembly was warranted. It was realized, of course, that the level of radioactivity of the components would necessitate extensive delays in the examinations. Since examination of a few critical ARE samples showed nothing unexpected, much of the planned hot-cell inspection was postponed and complete examination of all but a few specimens was indefinitely suspended. The few examinations that were completed are described in this report, along with a description of the disassembly of the ARE system. Diagrams of the fuel system, sodium system, and off-gas system are presented in Figs. 1, 2, and 3 for reference use in visualizing the disassembly process.
Date:
April 15, 1958
Creator:
Cottrell, W. B.; Crabtree, T. E.; Davis, A. L. & Piper, W. G.
Object Type:
Report
System:
The UNT Digital Library
Some Experiments Relating Ion Diffusion in a Plasma to the Neutral Gas Density in the Presence of a Magnetic Field
In some recent experiments the ion density in a plasma was measured as a function of radial distance from a d-c arc source of ions for the magnetic field intensities from 2500 to 14000 oersted. The diffusion coefficient appeared to very inversely as the square of the magnetic field strength, D~1/H2. The absolute value of D was shown to be approximately that which would be predicted by the collision diffusion theory when account is taken of the shorting effect of the end walls. The purpose of this report is to continue the examination of ion diffusion in a plasma and field experimentally the relation between the diffusion coefficient and the neutral gas pressure for a constant magnetic field.
Date:
June 15, 1956
Creator:
Reidigh, Rodger V.
Object Type:
Report
System:
The UNT Digital Library
House Bill 3 Student to Teacher Ratio Report
This report describes report to the legislature based on the information collected from each school district that offers a prekindergarten program and each private entity that provides a prekindergarten program under contract with a school district for each prekindergarten class offered by the district or private entity.
Date:
January 15, 2021
Creator:
Texas Education Agency
Object Type:
Report
System:
The Portal to Texas History
Texas Register, Volume 47, Number 15, Pages 1945-2070, April 15, 2022
A weekly publication, the Texas Register serves as the journal of state agency rulemaking for Texas. Information published in the Texas Register includes proposed, adopted, withdrawn and emergency rule actions, notices of state agency review of agency rules, governor's appointments, attorney general opinions, and miscellaneous documents such as requests for proposals. After adoption, these rulemaking actions are codified into the Texas Administrative Code.
Date:
April 15, 2022
Creator:
Texas. Secretary of State.
Object Type:
Journal/Magazine/Newsletter
System:
The Portal to Texas History
Fabrication Procedure For RaLa Source Fuel Rods
A new method to procure RaLa sources was proposed by Group CMR-10, Los Alamos Scientific Laboratory. This method depended upon irradiation of small-diameter U235 wire in the Materials Testing Reactor, Arco, Idaho. A procedure for cladding and sealing U235 wire in stainless steel tubing, by drawing, plugging the tube ends, and welding, was developed, tested, and proved to be satisfactory.
Date:
February 15, 1956
Creator:
Hockett, J. E.; Duncan, J. D.; Doll, D. T. & Taub, J. M.
Object Type:
Report
System:
The UNT Digital Library
Recovery of Manganese Dioxide From Rand Barren Solutions
In the course of recovering uranium from Rand cyanide residues, large volumes of barren acid liquors are produced. With the flowsheets now under consideration it is not advisable to recycle such liquors and they are to be discarded. Consideration was given to the removal of manganese under conditions that would permit its recovery as MnO2.
Date:
March 15, 1953
Creator:
Owens, Albert W.
Object Type:
Report
System:
The UNT Digital Library
Utex Leaching, Thickening and Filtration Tests
A series of leaching, thickening, and filtration tests was undertaken to determine minimum conditions for high uranium extractions and to obtain thickening and filtration data.
Date:
March 15, 1954
Creator:
Stanley, Alan; George, D'Arcy R.; Thomas, Peter N.; Eisenhauer, Robert; Lynch, James T. & Richardson, Stanley
Object Type:
Report
System:
The UNT Digital Library
Investigations of Ion Exchange Methods for Recovery of Uranium From Liquors Produced by Acid Leaching of Gunnar Ore
An ion exchange testing program was completed on Gunnar acid leach liquors and pulps. A standard column system and a resin-in-pulp system, both using anion exchange resins, were investigated. The Gunnar leach liquors are readily amenable to the recovery of uranium by ion exchange.
Date:
June 15, 1954
Creator:
Schiff, Norman N. & Lower, George W.
Object Type:
Report
System:
The UNT Digital Library