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709 Program for Reduction of Exponential Pile Data

Description: A multi-purpose program for processing exponential data has been prepared for the 709 computer. The main purposes of the program is to compute the material buckling from raw data (given counts, time, and counter information) or from previously calculated Athermal's. It is also possible to compute only CeCh (end and harmonic corrections) for a given B11 or series if B11's no counting data being entered. In every case, pile measurements must be submitted as input for corrections.
Date: August 20, 1959
Creator: Matsumoto, D. D.
Item Type: Refine your search to only Report
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Analysis of a Nuclear Incident in a Redox Dissolver

Description: Since the start of E-metal processing in December, 1958, critical mass control in the Redox dissolvers has been provided by a combination of administrative controls, revised dissolver charging procedures, and new dissolving processes and operation control procedures. These were all based on a maximum allowable charge of E-Metal to the dissolvers which was equivalent to 45 percent of the minimum critical mass.
Date: August 24, 1959
Creator: Neely, V. I.
Item Type: Refine your search to only Report
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Backmixing in Pulse Columns II, Experimental Values and Effect of Several Variables

Description: Seven runs were made with the system Penn. Ref. Co. "Supersol" (dispersed) water (continuous) to investigate the effects of pulse frequency, amplitude plate spacing, volume flow ratio, and throughput on backmixing, using the technique of continuous injection of a tracer solution into the packed section. Backmixing was found to be surprisingly insensitive to all the above variables over the range studied with the exception of pulse amplitude and continuous phase flow rate, showing greatest depe… more
Date: August 11, 1953
Creator: Swift, W. H. (Ward Henry), d 1929- & Burger, L. L.
Item Type: Refine your search to only Report
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Behavior of S.I.R. Fuels Irradiated in Sodium: Final Report, Production Test 105-180-P (Special Request KAPL-79: The "Beta Experiment")

Description: Report describing the effects of pile irradiation on fuel materials and coil springs for the Submarine Intermediate Reactor. The investigation was called for by Hanford Irradiation Request No. 79. Results of investigation are detailed in the report.
Date: August 12, 1952
Creator: Lambert, J. B., 1929-
Item Type: Refine your search to only Report
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A Closed Circuit Television System for In-Well Use -- Interim Report

Description: Wells drilled to date on the Hanford project represent and initial investment of over one million dollars. These nearly six hundred wells have been used and will continue to be used for observation and monitoring purposes of direct interest to ground disposal of radioactive wastes. Through measurement of depth to the water table the changing gradients as a result of large volume waste disposal are determined and direction of ground water flow established. The extent of contamination in ground … more
Date: August 5, 1959
Creator: Ratcliffe, C. A.
Item Type: Refine your search to only Report
open access

Corrosion of Redox Waste Storage Tank Construction Materials

Description: From introduction:"It was the aim of this investigation to determine the resistance of several materials of construction to current and anticipated and anticipated Hanford separation process waste streams under specific conditions. The corrosion rates of mild steel and austenitic stainless steel and the resistance of several commercial protective coatings were established."
Date: August 21, 1950
Creator: Koenig, W. W. & Sanborn, K. L.
Item Type: Refine your search to only Report
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The Coulometric Determination of Acetic Acid

Description: Abstract: "Small amounts of acetic acid, equivalent to 400 ul. of 0.3 to 0.13 g/L. can be titrated coulonatrically in the presence of a 10 to 25-fold excess of HN03 in 70%, isopropanol. An accuracy of +/- 0.1% and a precision of +/- 8.5% (99% limite) are obtained.
Date: August 16, 1949
Creator: Carson, W. N. & Ko, Roy
Item Type: Refine your search to only Report
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Criticality of Fuels of Low Enrichment in Cylinders

Description: Maximum safe cylinder diameters, slab thicknesses, and minimum critical masses in spherical geometries for fuel of < 5.0& U-235 enrichment have been evaluated. It is of interest to know the minimum critical masses as a function of cylinder diameter for vessels that are not safe by geometry. Curves will be presented of critical masses as a function of cylinder diameter and fuel rod size for 1.6%, 3.0%, and 5.0% U-235 enriched metal-water systems.
Date: August 14, 1959
Creator: Ketzlach, N.
Item Type: Refine your search to only Report
open access

Diffusion of Stack Gases in Very Stable Atmospheres: Case II

Description: In 1949 Barad presented two solutions to the general diffusion equation. Basic in both solutions is the assumption that in very stable atmospheres a point source may be replaced by a vertical area of uniform concentration at a short distance downwind. This vertical area is considered to exist at the distance at which the plume finally "levels-off" and assumes a flat ribbon-like appearance. In addition if the distance over which diffusion takes place is limited to one or two miles and if only… more
Date: August 10, 1953
Creator: Barad, M. L. & Shorr, B.
Item Type: Refine your search to only Report
open access

Division of Reactor Development Programs Monthly Report- July 1959

Description: Basic Studies. Sinterability studies on the isomorphous system UO2-PuO2 have continued. One-half inch diameter X 3/8'' long compacts containing physical mixtures of the two components have been heated in hydrogen. Sintered density as a function of time and temperature has been determined for times of one and eight hours up to 1600 C. In general, there seems to be minima on isothermal plots of density versus composition in the intermediate range 20-40 w/o PuO2. At concentrations greater than 40 … more
Date: August 17, 1959
Creator: McEwen, L.H.
Item Type: Refine your search to only Report
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Eddy Current Ultrasonic Transducer

Description: In the field of nondestructive testing the ultrasonic test method is used extensively. In this method ultrasonic energy generated by a transducer is caused to enter the test specimen. The effect on the transducer is cause to enter the test specimen. The effect on the transmission or reflection of the ultrasonic energy by differing test specimen structure is used as an indirect measure of test specimen characteristics.
Date: August 24, 1959
Creator: Libby, Hugo L.
Item Type: Refine your search to only Report
open access

Effect of Temperature on Uranium Recovery Columns Operation

Description: Some data on the temperature effect in pulse columns are reviewed. New data obtained with the "vibrational" stirrer are reported. The effects on both the dispersion and coalescence and the net rate of extraction suggest that improved operation of the RA column and lowered waste losses would be expected at elevated temperatures.
Date: August 12, 1953
Creator: Burger, L. L.
Item Type: Refine your search to only Report
open access

Eurochemic Questions -- Preliminary Report

Description: The referenced memo asked several questions on the operation of the Purex Plant which are of interest to the Eurochemic personnel. These questions are answered below. 1. A qualitative description of the nitric acid recovery systems is desired -- flow of materials, number of pieces of equipment, etc.
Date: August 24, 1959
Creator: Geier, R. G.
Item Type: Refine your search to only Report
open access

Field Experiments with Model Crib I. Location, Facility Design and First Experiment

Description: One of the research studies of the Chemical Effluents Technology Operation is the improvement of the method for predicting the capacity of a crib for the retention of wastes. In addition to laboratory work the research was extended a field experiment using a simulated crib fed with a solution containing a radioactive tracer. The purpose is twofold: (1) to check the validity of laboratory findings and (2) to observe several features of the behavior of solutions put to ground in the field.
Date: August 4, 1959
Creator: Knoll, K. C. & Nelson, J. L.
Item Type: Refine your search to only Report
open access

Hazards Summary Report for the Hanford Plutonium Critical Mass Laboratory

Description: Report that summarizes the potential hazards of the Hanford Critical Mass Laboratory and presents operation procedures which will limit the probability of a nuclear accident. The report also outlines the planned experimental program, descriptions of the facility, and the administration of nuclear safety in the laboratory.
Date: August 1, 1960
Creator: Reardon, W. A.; Clayton, E. D.; Brown, C. L.; Masterson, R. H.; Powell, T. J.; Richey, C. R. et al.
Item Type: Refine your search to only Report
open access

Heat Transfer Calculations for CO2 Gas-Cooled Loop-PRTR

Description: At the request of Design Development Operation, various heat transfer and fluid flow problems were examined which are peculiar to the CO2 Gas-Cooled Loop in the PRTR. The results of these calculations are desired primarily to aid in demonstrating the adequacy of the design proposal. In addition, the operational limits of the loop and the consequences of the gas loop installation on the PRT reactor are of interest.
Date: August 4, 1959
Creator: Muraoka, J.
Item Type: Refine your search to only Report
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