Search Results

A Preliminary Comparison of the Nannoplankton and Net Plankton of the Columbia River

Description: Plankton collected from the Columbia River by the net method and by the centrifuge method were compared. The centrifuged plankton (nannoplankton) exceeded the net plankton in weight, in abundance of organisms and in radioactivity. Similar seasonal trends were present in both types of plankton.
Date: September 10, 1953
Creator: Coopey, R. W.
Partner: UNT Libraries Government Documents Department

An Ionization Chamber Method for the Standardization of Tritiated Water Samples

Description: Ionization measurements of water vapor in vapor-liquid equilibrium were made with a series of chambers on a tritiated water sample which was prepared by burning T2 to T2O and diluting it with H2O. A correction was made for the difference of vapor pressures of HTO and H2O. The effect of HTO adsorbed on chamber walls and electrodes was eliminated from the final result. Using Gerbes data on the number of electron volts to produce an ion pair in air, agreement obtained between the measured source strength and the source strength as computed from pressure, temperature, volume, purity, and dilution data on the original gaseous T2 sample.
Date: July 23, 1953
Creator: Myers, I. T.
Partner: UNT Libraries Government Documents Department

A Continuous Gamma Activity Monitor for the Product Stream of the Uranium Recovery Plant

Description: A continuous gamma-monitoring instrument capable of measuring the activity of the product of the Uranium Recovery plant has been developed and applied under process conditions. It has a detection limit of 15% and a normal range of up 1000% of the activity of natural uranium. Activity measurements made with this instrument have shown good correlation with laboratory determinations and are contributing to improved control of the solvent extraction process.
Date: October 1, 1953
Creator: Leboeuf, M. B.; Connally, R. E. & Upson, U. L.
Partner: UNT Libraries Government Documents Department

The Determination of Cu-64 in Reactor Effluent Water by Electrodeposition

Description: An analytical method for Cu-64 in reactor effluent has been studied based upon electrodeposition of the active copper with inert copper carrier. A two hour plating time was employed at a current density of 10 ma/sq cm and four volts across the cell. A stainless steel cathode plate was used. Carrier yields of greater than 80% were obtained with a standard deviation of the yield-corrected counting rate as low as 0.24%. Very little, if any contamination by other radioactive elements present was shown by decay curve studies. Self-absorption and self-scatter factors to correct the counting rate were obtained.
Date: September 16, 1953
Creator: Perkins, R. W. (Richard W.)
Partner: UNT Libraries Government Documents Department

Abrasive Cutting of Irradiated Uranium

Description: The preparation of radioactive metallurgical specimens for microscopic examination is one of the responsibilities of the Radiometallurgy Sub-Unit. An abrasive cut-off machine development program, based upon a previous experimental model, was undertaken to provide a method for sectioning of irradiated materials without undue personnel exposure or spread of contamination and finally to provide data for the design of an abrasive cutting unit for use in the work cells in the Radiometallurgy Building. A horizontal-feed type set-off machine, powered by a 7 1/2 hp motor with V-belt drive, has been developed for the submerged sectioning of irradiated uranium and is currently being used successfully to obtain samples for metallurgical, chemical and physical investigations without excessive personnel exposure or spread of radioactive contaminates.
Date: September 17, 1953
Creator: Boyd, Carl L.
Partner: UNT Libraries Government Documents Department

Elastic Analysis of Stress Conditions in a Reduction Bomb (Task III Replacement Pressure Vessel Model-1302)

Description: Several failures have occurred in reduction bombs used in metal production operations. A test program is being initiated to evaluate new metals for the construction of the bomb. In the test program, a tensile specimen is cycled through temperatures simulating operating temperatures, and the time to rupture is recorded in order to estimate the life in operation of a reduction bomb made with the candidate metal. In order to find the worst stress condition, the compressive, hoop, and bending stresses must be considered.
Date: February 19, 1954
Creator: Merckx, K. R.
Partner: UNT Libraries Government Documents Department

Laboratory Corrosion Tests of Spring Steel Wire in Simulated Neutralized Purex Process Waste Solution

Description: The purpose of the short duration corrosion test was to obtain preliminary data regarding the corrosion resistance of the spring steel wire in Purex process waste solutions and to measure any changes in the tensile properties of the wire resulting from this exposure.
Date: October 16, 1953
Creator: Endow, N.
Partner: UNT Libraries Government Documents Department

Laboratory Development of an Electromagnetic Test for Uranium Quality

Description: An electromagnetic instrument similar to the Multitest was built and used to test 2200 uranium slugs. It was found that the equipment could be used to detect inclusions and cracks in the uranium, but that small cracks are not readily detectable on a production basis unless the material is absolutely uniform in inclusion content. The instrument can be used, however, to sort out hidden defects of a reasonable size and to reject grossly dirty uranium.
Date: March 30, 1954
Creator: Headrick, H. B. & Wood, E. C.
Partner: UNT Libraries Government Documents Department

Hazards of Exposure to Tritium and Tritium Oxide

Description: Experimental data pertinent to the evaluation of hazards involved in the exposure of personnel to tritium and tritium oxide are reviewed. Conclusions are drawn and recommendations made with regard to the control of these hazards.
Date: January 1, 1954
Creator: Thompson, Roy C. & Kornberg, H.A.
Partner: UNT Libraries Government Documents Department

Some Comments on the Selection of Operating Temperatures for DPR

Description: The results of this investigation indicate that maximum electric power generation can be obtained by selecting the turbine steam temperature within a range of plus/minus 30 degrees C. from an "idealized" steam temperature. This "idealized" steam temperature is shown to depend primarily on the maximum permissible uranium temperature. The minimum available condenser temperature and the temperature rise of the coolant in the pile effect the selection of the turbine steam temperature to lesser extent.
Date: November 16, 1953
Creator: Altmann, Manfred.
Partner: UNT Libraries Government Documents Department

Final Report: Production Test No 105-505-SI. Exposure of Two Different Types of Rubber to Pile Water

Description: In connection with different seals for C & D equipment it appears advantageous that many parts could be made of rubber or other elastic polymers. However, data on the deterioration rate of these materials under irradiation are somewhat scant in the available literature. It appears that for neutrons and pure gamma radiation that a good grade of natural rubber stands up best in all the test reported and because the results of the neutron irradiation are so closely correlated with results from gamma it has been proposed that the principal source of damage is caused by secondary irradiation generated within the rubber by the neutrons.
Date: November 18, 1953
Creator: Cooke, J. P.
Partner: UNT Libraries Government Documents Department

Comparison of Descaling Solutions for Aluminum Alloys

Description: A laboratory test was performed to determine if a 10% oxalic acid solution could be safely be employed as a substitute to 2% chromic acid plus 5% phosphoric acid for removal of corrosion products from aluminum corrosion samples or slugs.
Date: September 2, 1953
Creator: Dairymple, R. S.
Partner: UNT Libraries Government Documents Department

Functional Testing and Operating Manual for Consolidated Helium Leak Detector, Model 24-101A

Description: A pile gas leak detection system consisting of a purchased mass spectrographic type of helium detector, a long sampling line for use in remote or relatively inaccessable locations, a pump to pull a continuous sample of gas from the tip of the probe to the detector, and a rotameter to measure the gas flow rate in the sampling line has been developed, calibrated, operationally tested. The system is practical for use in locating all pile gas leaks larger than about 0.1 cubic foot per hour.
Date: September 11, 1953
Creator: Spencer, H. G.
Partner: UNT Libraries Government Documents Department

Investigation of Redox D-12 Waste Concentrator No. 2 Coil Nest Failure

Description: Four D-12 coil nests have failed since the start-up of the Redox Separations plant. Due to the high contamination and radiation levels of these vessels, the cost of decontamination has prevented the examination of all but one of the four. It was hoped that the examination of D-12 pot #2 would lead to an explanation of all four failures. This report will deal primarily with the metallurgical examination of the failure of D-12 pot #2.
Date: March 2, 1954
Creator: Groves, N. D. & Smith, W. R.
Partner: UNT Libraries Government Documents Department

A Study of Plutonium Trifluoride Precipitated from Aqueous Solution

Description: In view of the increasing number of methods for determining plutonium in terms of weight rather than radioactivity, a need has arisen for a plutonium compound that can be used as a gravimetric standard. An easily prepared compound that dissolves readily in nitric acid is desirable. The present study was made to determine the feasibility of using plutonium triflouride as a plutonium standard. The preparation, composition, stability, and ignition of the compound are discuss, as are certain properties of the plutonium dioxide resulting from ignition of the trifluoride.
Date: December 28, 1953
Creator: Jones, M. M. (Miriam M.).
Partner: UNT Libraries Government Documents Department

Variation of Diffusion Length with Sigma-Pile Size

Description: The investigation to be described in this paper was one of several undertaken to resolve a curious discrepancy that had arisen in measurements of the diffusion length of graphite. Those diffusion lengths measured with the graphite layups of 100 Area piles were three to six centimeters higher than the value obtained with the Hanford Standard Pile. The fact that the 100 Area structures of the order of 40 ft. X 40 ft. X 30 ft, not including reflector, approximated an infinite medium, whereas sigma piles are of the order of 8 ft. X 8ft. X 10 ft., suggested the possibility that the diffusion length obtained by mensuration of relative fluxes and application of the conventional equations depended in some way on the size of the medium. Therefore, in order to determine if such a dependency actually exists, it was proposed to erect a series of graphite stacks of different dimensions and to make diffusion length measurements in each.
Date: January 4, 1954
Creator: Block, E. Z. & Davenport, D. E.
Partner: UNT Libraries Government Documents Department

Estimated Power Generation in MTR Slug Test Facility

Description: The very strong flux gradient in the MTR reflector might be thought to be some cause of worry. However, this gradient will be minimized by the presence of the large block of aluminum, which, because of its small effect on neutrons, will tend to flatten the neutron flux in its vicinity. Advantage should be taken of the shape of the test facility by placing the water hole corner closest to the MTR core. This placement should take best advantage of the flattening potentialities of the slowing-down flux from the test slugs, by placing the nearest (beryllium) moderator on the low flux side of the assembly.
Date: December 30, 1953
Creator: Neumann, Hans, 1936-
Partner: UNT Libraries Government Documents Department

Maximum Temperature in Thin Rectangular Uranium Wafers

Description: Temperature calculations have been made to aid in planning a production test for low level irradiation of the thin rectangular uranium wafers. These uranium wafers, under irradiation in the outer fringe sone, are expected to have a maximum temperature which is less than 10 C above the local water temperature.
Date: January 6, 1954
Creator: McNutt, C. R.
Partner: UNT Libraries Government Documents Department

Standard Practices Counting Manual

Description: The purpose of this manual is to present available data which can be used to determine disintegration rates of radioactive samples from counting rates measured under given circumstances with routinely used laboratory instruments. There is also brief discussion on the methods by which the various factors have been determined with reference to the accuracy with which they are known and to what extent the finally quoted disintegration rate is affected by these errors. Emphasis has been placed on those isotopes of particular interest to Radiological Sciences programs and the manual is intended as a standard through the use of which comparable values can be reported from all units in the Department.
Date: January 4, 1954
Creator: Schwendiman, L. C.
Partner: UNT Libraries Government Documents Department

The Resistance of Various Bearing Materials to Chemical Attack by Nitric Acid and Uranyl Nitrate Hexahydrate

Description: The purpose of this study has been to evaluate the chemical resistance of various bearing materials to solutions of nitric acid and uranyl nitrate hexahydrate with views toward selecting the best material to be used as bearings in Purex submerged rotating equipment.
Date: March 11, 1954
Creator: Groves, Norman D.
Partner: UNT Libraries Government Documents Department

Teflon Bellows Pulse Generators for Solvent Extraction Pulse Columns

Description: The feasibility of using Teflon bellows as the pulsing device for solvent extraction pulse columns has been previously demonstrated by life test of various sizes of Teflon bellows. This report describes a compact Teflon bellows pulse generator and drive assembly which was designed, built, and tested by the Chemical Development Unit. The pulse generator assembly is suitable for a number of applications where pulse generators are required to pulse solvent extraction columns.
Date: January 1, 1954
Creator: McCarthy, P. B.
Partner: UNT Libraries Government Documents Department

The Hanford Remote Pipetter

Description: The Hanford Remote Pipetter has developed into a very useful tool for routine pipetting by semi-skilled non-technical personnel. Radiation exposure to the operators has decreased to normal background levels as proper shielding exists between the sample and the operator. The results achieved by the pipetter have demonstrated its flexibility and simplicity of operation.
Date: January 15, 1954
Creator: Hammill, K. H.
Partner: UNT Libraries Government Documents Department