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Internally Cooled Molten-Salt Reactors

Description: The initial and long-term nuclear characteristics of two internally cooled heterogeneous, graphite-moderated, two-region, molten-salt reactors have been studied. These reactors have doubling times of 22.5 years and 27.5 years. Methods of decreasing the doubling times by removing the Pa233 from the core and be increasing the specific power of the reactor are described.
Date: June 22, 1959
Creator: Lackey, M. E.
Partner: UNT Libraries Government Documents Department
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Hexone Extraction-Coulometric Titration of Uranium

Description: Samples containing 5 to 10 mg of uranium were extracted with hexone (methyl isobutyl ketone) and titrated coulometrically in sulphate media. Relative standard deviations of 0.45% for samples containing 5 mg and 0.56% for 10 mg were determined by precision studies.
Date: June 22, 1959
Creator: Blevins, E. L.
Partner: UNT Libraries Government Documents Department
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Report of Fire in Laboratory Hood, Wing I, Building 4500

Description: The fire involved approximately 30 liters of isopropyl alcohol as a result of the ignition of about 16-18 liters of isopropyl alcohol and a slurry of thoria and ammonium nitrate in a 20-liter glass carboy. This material was undergoing a volume reduction by boiling in a floor-type metal hood with Plexiglas sides and 3 sliding door on the front of ordinary glass. The alcohol vapor was vents directly into the hood (Fig1.)
Date: May 22, 1959
Creator: Lain, J. E. & Hungerford, T. W.
Partner: UNT Libraries Government Documents Department
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Preliminary Report on 2% U235-Enriched UF4-C25H52 Critical Assemblies

Description: A series of critical experiments with blocks of 2% U235-enriched UF4-C25H52 has been initiated at the ORNL Critical Experiments Facility. Thus far assemblies with H:U235 atomic ratios of 195 and 294 have been built in parallelepipedal and simulated cylindrical geometries, both reflected and unreflected. From the results the minimum critical masses for reflected spheres have been determined to be 16.3 and 8.5 kg of U235 for fuel mixtures with H:U235 atomic ratios of 195 and 294, respectively. Th… more
Date: April 22, 1959
Creator: Mihalczo, J. T.; Lynn, J.J.; Scott, Dunlap & Connolly, W. C.
Partner: UNT Libraries Government Documents Department
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Protection of Carbon Steel from Atmospheric Corrosion

Description: The NPR design calls for carbon steel to be the major constituent in the reactor coolant piping system. The piping and its associated fittings will, in all likelihood, be exposed to atmospheric weather conditions during the period of reactor construction. This type of exposure causes rusting. From experience gained during the startup of KER Loop 1 it is expected that there will be initially high NPR coolant activity levels. The high activity during the startup of KER Loop 1 was partially caused… more
Date: October 22, 1959
Creator: Perrigo, Lyle D., Jr. & Moles, R. G.
Partner: UNT Libraries Government Documents Department
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Soil Column Studies with Radiostrontium I. Effects of Temperature and of Species of Accompanying Ion

Description: Soil chemistry studies have been carried on at Hanford for a number of years in support of the disposal of low and intermediate level liquid wastes to the ground. Equilibrium type experiments were carried out to investigate the mechanisms of the reactions of Sr, Cs, and rare earth ions with soils (1, 3, 4, 5). Experiments were also conducted with simulated and actual wastes in soil columns and an empirical method was developed for prediction of radionuclide breakthrough from ground disposal fac… more
Date: September 22, 1959
Creator: Nelson, J. L.
Partner: UNT Libraries Government Documents Department
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3 Plant Radiation Study Interim Report #5- Part II Data on Gamma Shielding of Special Plutonium Samples

Description: The calculation of shielding the thickness for plutonium is complicated by the many different energies represented in the gamma radiation emitted during decay of the plutonium isotopes. Dose rate predictions are also frequently confused by gamma from varying content of fission product impurities in the plutonium, as well as other gamma radiation induced through alpha and neutron particle absorption within the source material or its environment. After assumptions are made for these many factors… more
Date: October 22, 1959
Creator: Moulthrop, H. A.
Partner: UNT Libraries Government Documents Department
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A Microspark Apparatus for the Study of Inclusions in Metals

Description: A study of metallurgical problems resulting from variation in grain boundaries, bonding layers, and inclusions in metals and alloys has become increasingly important over the past several years. To keep pace with and aid in these studies, several new techniques have been developed in emission and X-ray spectroscopy. In X-ray, areas as smalls as one square micron can be studied by making them targets for a focused electron beam and observing the X-rays emitted (5,2). Such an instrument would be … more
Date: July 22, 1959
Creator: Smith, F. M.
Partner: UNT Libraries Government Documents Department
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The Effect of Solution and Vessel Thermal Expansion on Volume Measurements in the Chemical Processing Department

Description: The major portion of transfers and inventory in the Chemical Processing Department are dependent on volume measurement. Good volume measurements are therefore essential to good SS material control. Considerable attention has been given to the volume problem especially on primary transfer points. Document HW-57888 discusses the biasing effect pf temperature on manometer oil. HW- 57866 given the procedure for vessel calibration. Other undocumented correspondence has discussed recent calibrations … more
Date: May 22, 1959
Creator: Johnson, W. R.
Partner: UNT Libraries Government Documents Department
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Limitations for Existing Storage Tanks for Radioactive Wastes from Separations Plants

Description: Continued process improvements in the separation plants provide an incentive for economics in waste storage costs by utilizing existing facilities to their maximum capability consistent with the radiological hazards involved. The major improvements have reduced waste volumes resulting in increased fission product concentration and energy potential. Analyses have been made to determine the effect of this change on the integrity of the existing structures.
Date: October 22, 1959
Creator: Doud, E.
Partner: UNT Libraries Government Documents Department
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Composition of Solids from Purex LWW

Description: The solids in Purex lww were first observed during flowsheet tests for recovery of fission products from plant wastes. Since the nature of this solid was not apparent from the flowsheet composition of lww, some work was performed to characterize this material. Although this work has been conducted over a period of about one year, it has been subordinate to the main one of testing flowsheets for fission product recovery. The solids have been observed in each of about six samples of plant lww tha… more
Date: January 22, 1959
Creator: Van Tuyl, H.H.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department Monthly Record Report: September 1959

Description: This document details activities of the irradiation processing department during the month of September, 1959. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.
Date: October 22, 1959
Creator: Greninger, A. B.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report, June 1959

Description: Production of Pu from separations plants and output of unfabricated Pu exceeded commitments. Purex plant set a new record high for U processed. Production and shipments of UO{sub 3} met schedules. Purex solvent extraction battery performed below normal, probably because of poor solvent quality. NaOH addition to Redox coating removal waste is being reduced. A 3fold improvement in Recuplex product Al impurity was achieved by means of a specific gravity difference > 0.15 between dilute aqueous fee… more
Date: July 22, 1959
Creator: MacCready, W. K.
Partner: UNT Libraries Government Documents Department
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Revised recommendations for the 100-K Area Project CG-775 raw water requirements

Description: As a part of Project CG-775, 100-K Area Water Plant Expansion, the capacity of the 181-K river pump installations will be increased. Recommendations for the raw water requirements based on a reactor flow of 175,000 gpm were presented in document HW-55877. Since then a new fuel element has been developed for the K reactors, resulting in a lower reactor system curve. It is recommended that the design criteria for the 181-K river pumps be based on a total raw water flow of 213,000 gpm with spare p… more
Date: June 22, 1959
Creator: Fifer, N. F.
Partner: UNT Libraries Government Documents Department
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190-C pump capacity

Description: The purpose of this document is to update 190-C pump capacity information previous released in HW-52449{sup 1} and HW-58580{sup 2}. Improvements in motor cooling has resulted in raising the previous 3500 HP limit to 3660 HP{sup 3} thus increasing total pumping capacity.
Date: June 22, 1959
Creator: Watson, D. F.
Partner: UNT Libraries Government Documents Department
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Hanford Atomic Products Operation annual report 1958

Description: This annual report (1958) from the Hanford Atomic Products Operation. Various programs are briefly described including irradiation processing, fuels preparation, chemical processing, research and development, and supporting operations.
Date: April 22, 1959
Partner: UNT Libraries Government Documents Department
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Design of production test IP-297-A-FP, The effect of autoclave film damage on the incidence of groove pitting on X-8001 alloy fuel jackets

Description: The recent increase in the incidence of groove pitting on X-8001 clad fuel elements in the old reactors apparently refutes the earlier hypothesis that surface segregation of the secondary phase of this alloy was the primary cause of the unique, preferential attack sustained during irradiation. Components received within the past fifteen months have exhibited essentially none of the segregation. On the other hand, recent evidence suggests that localized penetration of the autoclave film on X-800… more
Date: December 22, 1959
Creator: Hall, R. E. & Hodgson, W. H.
Partner: UNT Libraries Government Documents Department
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A Wide-Range Neutron Detector and Monitoring Instrument : Final Report

Description: This is the final report on the progress, "A Wide-Range Neutron Detector and Monitoring Instrument," ARF 1118-6. This report covers activities from May 8, 1958 to May 8, 1959. This report describes the basic design principles of a proportional counter that has been constructed whose cathode diameter increases towards one end.
Date: April 22, 1959
Creator: Porges, K. G.
Partner: UNT Libraries Government Documents Department
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High Current Electron Accelerator

Description: The following report describes the investigations of the microwave solution and the Astron solution, to produce high current electron beams.
Date: January 22, 1959
Creator: Christofilos, Nicholas C.
Partner: UNT Libraries Government Documents Department
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Temperatures and Thermal Stresses in Hexagonal Tubes and Pierced Plates With Internal Heat Sources

Description: From abstract: "Steady temperatures and thermal stresses are determined for long hexagonal tubes having round holes for the case of uniform internal heat generation and a fluid-cooled inside surface. Thermal stresses are also determined for thick plates pierced by holes on an equilateral triangular pattern and for hexagonal tubes having a hexagonal hole with rounded inside corners. Stresses in the end regions of tubes are also investigated."
Date: September 22, 1959
Creator: Meuser, Robert B.
Partner: UNT Libraries Government Documents Department
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Limitations for Existing Storage Tanks for Radioactive Wastes From Separations Plants

Description: The physical limitations of existing storage tanks for radioactive wastes from separations plants are defined as a guide for preparing process and operating criteria for the existing tank forms to assure continued integrity of the tanks. A "safe-load" curve for each of the four groups of tanks based on current technology is presented. Loading conditions, operation procedures, and thermal stresses are discussed. (M.C.G.)
Date: October 22, 1959
Creator: Doud, E. & Stivers, H.W.
Partner: UNT Libraries Government Documents Department
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PRELIMINARY REPORT ON 2% U$sup 235$-ENRICHED UF$sub 4$-C$sub 25$H$sub 52$ CRITICAL ASSEMBLIES

Description: A series of critical experiments with blocks of 2% U/sup 235/--enriched UF/sub 4/-C/sub 25/sub 5/H/sub 52/ was initiated at the ORN L Critical Experiments Facility. Thus far assemblies with H:U/sup 235/ atomic ratios of 195 and 294 were built in parallelepipedal and simulated cylindrical geometries, both reflected and unreflected. From the results the minimum critical masses for reflected spheres were determined to be 16.3 and 8.5 kg of U/sup 235/ for fuel mixtures with H:U atomic ratios of 195… more
Date: April 22, 1959
Creator: Mihalczo, J T; Lynn, J J; Scott, D & Connolly, W C
Partner: UNT Libraries Government Documents Department
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THE THEORY AND DESIGN OF THE TRIGGERED SPARK GAP

Description: The basic theory of operation of the triggered spark gap is established, and qualitative and quantitative engineering design data are given. From the basic twoelectrode gap, a three-electrode or triggered gap model is established with its static and dynamic triggering characteristics shown. Several geometry conditions such as gap spacings trigger electrode hole sizes and insulator effects are discussed, showing their influence upon the triggering mechanism. A suggested trigger mechanism is give… more
Date: May 22, 1959
Creator: Williams, T.J.
Partner: UNT Libraries Government Documents Department
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