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Short Time Corrosion Tests of Bronze, Mild Steel, T-304 Stainless Steel and 2S Aluminum in 10% Potassium Tetraborate Solution

Description: Report summarizing corrosion tests meant to determine the corrosion rates of bronze, mild steel, T-304 stainless steel and 2S aluminum in 10% potassium tetraborate solution. Tests were completed under the boiling point of each solution except for 2S aluminum, which was tested at 40C, the approximate temperature in a pile.
Date: December 14, 1951
Creator: Katayama, Y. B.
Partner: UNT Libraries Government Documents Department
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PRPR Control Requirements. Part I.

Description: The following remarks are intended primarily to assist in the orientation of the PRP reactor control development program in a direction consistent with the basic objectives of the program as a whole, and to discuss certain aspects of particular control systems which have a bearing on the capabilities of the reactor with respect to these objectives.
Date: November 14, 1956
Creator: Triplett, J. R.
Partner: UNT Libraries Government Documents Department
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Feasibility of In Vivo Plutonium Measurements

Description: It was shown that without further major development the detectors proposed for the Body Monitor can be expected to detect 0.02 microcurie of plutonium at the center of the chest cavity. This is the permissible body burden of insoluble forms of plutonium. The detection level can be decreased by decreasing the background counting rate. Decreases in the background can reasonably be expected; it should be possible to detect a small fraction of the permissible body burden. If it can be shown, as sug… more
Date: May 14, 1956
Creator: Roesch, W. C. & Baum, J. W.
Partner: UNT Libraries Government Documents Department
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An Initial Study of the Wear and Galling of Various Fuel Element Support Materials of Autoclaved Zircaloy-2

Description: An ex-reactor test stimulating the charging of a tubular fuel element in a Zircaloy-2 process tube showed a problem of severe process tube scratching and galling may occur if metal sliding contact fuel element supports are used. Both the fuel supports and the process tubes were autoclaved. Although the conditions of this test were severe in that the sharp edges rather than a flat surface of the supports were in contact with the process tube, it pointed out the potential problem of galling by po… more
Date: January 14, 1960
Creator: Weber, J. W.
Partner: UNT Libraries Government Documents Department
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Continuous Denitration Status of Development, January 12, 1955

Description: Experimental studies on continuous denitration performed in 321 Building resulted in the development of an agitated-through-type calciner. The performance of a paddle-agitated 4-in.-diameter by 44-in.-long reactor was sufficiently promising to warrant construction of a 16-in.-diameter by 8 ft.-long semi-plant scale model. This progress report summarizes the results of studies to date employing the semi-plant scale calciner.
Date: January 14, 1955
Creator: Szulinski, M. J.
Partner: UNT Libraries Government Documents Department
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Examination of Irradiated Uranium-Chromium Alloy Slugs

Description: Production Test 313-105-13-M authorized the irradiation of a uranium - 0.4 atomic per cent chromium alloy to determine the relative stability of this material during irradiation. Five tubes, each containing six four-inch alloy slugs, were irradiated to exposures ranging from 156 to 834 MWD/T. This report describes the results of the visual examination of the bare uranium alloy slugs and the results of the test to determine slug breaking strength. The breaking strength of both the U-Cr alloy slu… more
Date: February 14, 1955
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Semi Works Studies for the Reduction of Corrosion-Product Impurities in UR-Plant UO3

Description: This report describes the work carried out in 321 Building semiworks equipment, to define the factors contributing to high corrosion-product contamination and presents recommendations for reducing the impurity level to meet current specifications (maximum of 200 parts total metals per million parts U).
Date: June 14, 1960
Creator: Amos, L. C.; Kirkendall, B. E. & Adler, K. L.
Partner: UNT Libraries Government Documents Department
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Surface Studies of Irradiated Graphite

Description: The effects of oxidation and irradiation on the microsurface structure of pile graphite have been investigated by measuring the surface area and pore size distribution of several samples. The results obtained for both oxidized and irradiated graphite samples indicate that changes in surface characteristics which occur are determined by the flux, temperature of irradiation, and gaseous atmosphere in which the radiation takes place.
Date: July 14, 1953
Creator: Spalaris, C. N.
Partner: UNT Libraries Government Documents Department
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Comparative Study of Alternative Fibrous Glass and Sand Exhaust Ventilation Air Filter Installations for Purex

Description: Unanticipated radioactive contamination of the 200 Areas environs was discovered in the latter part of 1947, about 2.5 years after the startup of the Bismuth Phosphate Separation Plants. It was subsequently established that this contamination was due to radioactive particles emanating from the Separation Plants' stacks, and the need for exhaust ventilation air filtration equipment was recognized. Sand filters were installed in the fall of 1948 in the ventilation systems of the B and T Bismuth… more
Date: December 14, 1953
Creator: Zahn, Lyle L., Jr.
Partner: UNT Libraries Government Documents Department
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The Identification of the Microscopic Angular Inclusions in Uranium

Description: Many procedures for the chemical isolation of the microscopic angular inclusions in rolled uranium have been investigated. Four were selected as most satisfactory for this work and will be described in detail. The procedures are: (1) the copper displacement of the uranium, (2) the electrolytic displacement of the uranium, (3) the chemical dissolution of the uranium in an anhydrous solution of hydrogen chloride in methanol, and (4) the chemical dissolution of the uranium in an aqueous solution… more
Date: December 14, 1953
Creator: Scott, F. A.
Partner: UNT Libraries Government Documents Department
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Anodic Etching Procedure for Uranium: Useful Lifetime of Baths Without Regeneration

Description: The useful lifetimes of the phosphoric-hydrochloric anodic etching solution and the nitric acid stripping solutions were studied. Groups of uranium wafers of surface areas approximately 0.033 sq ft were anodically etched and stripped. From the losses in weight observed, it was concluded that at least three square feet of uranium may be anodized per liter of phosphoric-hydrochloric acid solution without regeneration. The nitric acid stripping solution was found to be satisfactory for at least on… more
Date: December 14, 1954
Creator: Pitzer, E.C.; Katayama, Y. B. & Budke, W. C.
Partner: UNT Libraries Government Documents Department
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The Evaluation of Air Samples Containing Thorium and Daughter Products

Description: Equations for the quantity of thorium daughters on an air sampler after various times of collection and decay are derived and evaluated. The most limiting assumption is the constant concentration over the sampling period. Applications of these equations to measurement of decay curves, alpha energy analysis and the simultaneous solution involving measurements at the three decay times are discussed.
Date: March 14, 1955
Creator: Healy, J. W.
Partner: UNT Libraries Government Documents Department
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The Stability of Three Base Metal Thermocouples in Helium-Carbon Dioxide, Carbon Dioxide and Air at 300 C

Description: In support of an in-reactor thermocouple stability testing program now in progress, laboratory studies were made relative to the stability of thermocouple bundles similar to those projected for in-reactor use. Two sets of chromel-alumel, copper-constantan and iron-constantan thermocouples were held for extended periods at 300 C in successive atmospheres of 75% helium-25% carbon dioxide. 100% carbon dioxide and air. Thermocouple stability was verified by measuring emf's at the freezing point of … more
Date: April 14, 1959
Creator: Sako, J. H.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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Recovery of Plutonium from Chloride Slag and Crucible

Description: Neutron radiation can be greatly reduced by substituting plutonium trichloride for plutonium tetrafluoride in the dry chemistry step of metal preparation. Chloride processes are now common in the metal preparation industry, and the 234-5 Developmental Laboratory has shown plutonium trichloride can be satisfactorily prepared and reduced to the metal.
Date: August 14, 1959
Creator: Smith, R. C.
Partner: UNT Libraries Government Documents Department
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Integrated Radiological Instrumentation System Planning

Description: In recognition of the need for an integrated system plan for future development requirements for radiological instrumentation, this information report was written to provide the initial step concerning such a planning. The report is to be considered a basic information analysis of the present in-use plant radiological instrumentation, of the instrumentation now undergoing active development, and of the future development work contemplated.
Date: July 14, 1960
Creator: Spear, W. G.
Partner: UNT Libraries Government Documents Department
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Studies on the Hydraulic Characteristics of Purex Off-Gas Jets

Description: The design of the Purex Off-Gas Treatment Facility requires the use of new dissolver off-gas jets which will be installed in series with present jets in the Purex in-canyon "donut" jumpers. When the new jets are placed in operation, the motive air and steam supply services to the in-canyon jets will no longer be required and the in-canyon jets will become flow restrictions in the dissolver off-gas train. Calculated values of pressure drop across these "dead" jets at maximum off-gas rate varied … more
Date: March 14, 1956
Creator: Michels, L.R.
Partner: UNT Libraries Government Documents Department
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Neutron Irradiation of Sapphire (Al 2 O 3 )

Description: A centerless-ground, 0.25-in.-diam. by 0.75-in.-long sapphire single crystal exposed to an integrated thermal neutron flux of 2 x 10 19 nvt at a temperature of 350 deg C (660 deg F) did not change its dimensions appreciably simple beam, with slightly less force than was required to break a similar unirradiated rod. In a darkened room the irradiated sapphire begins to thermoluminesce noticeably at 280 deg C (535 deg F) and most of the amber or brown coloration produced by the pile exposure is re… more
Date: March 14, 1956
Creator: Wheeler, R.G.
Partner: UNT Libraries Government Documents Department
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A Continuous River Sampling System and Methods of Radiochemical Analyses for Strontium-89, 90, Barium-140, and Phosphorus-32

Description: The discharge of reactor cooling water to the Columbia River introduces an amount of radioactive material to the river. It was of interest to study the downstream dilution of specific isotopes and establish accurate concentration measurements for calculation of the radiological hazard and mass balance.
Date: January 14, 1957
Creator: Silker, W. B.
Partner: UNT Libraries Government Documents Department
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Procedures for Measurement of Aluminum Corrosion

Description: If consistent results are to be obtained in a corrosion program, all samples must be handled in a uniform manner throughout the program. The following procedures have been set up as standard for the Corrosion and Coatings Operation and have been used for all the aluminum corrosion tests in the group.
Date: January 14, 1957
Creator: Bowen, H. C. & Thiede, R. A.
Partner: UNT Libraries Government Documents Department
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