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A Device for Continuous Detection of Hydrogen in Sodium

Description: Abstract: A device to detect the presence of hydrogen in sodium has been developed. Such a device, installed in a sodium heated steam generator, would signal the presence of water in the sodium resulting from a leak in the sodium-water barrier.
Date: December 15, 1960
Creator: Strahl, H.
Partner: UNT Libraries Government Documents Department
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Fuel element study for Reactor Overbore Program

Description: Recent studies have confirmed that large incentives exist for overboring the reactor process channels approximately 500 mils in the C and five old reactors under the proposed Plant Improvement Program. Conservative estimates of the incentives for overboring indicate a payout period of about two years for the proposed work, an increase in plutonium production of 15--18%, derived from increased conversion ratio and a reduction in plant unit cost. Since sufficient progress has been made in the areas of reactor development to warrant the necessary planning and budgetary action to accomplish the proposed work, a preliminary study has been conducted to determine and assess the technical problems associated with the processing and performance of oversize fuels, to define those areas requiring further development, and to provide cost estimates for the conversion and operation of both offsite uranium fabrication facilities and HAPO fuel manufacturing facilities as required to produce oversize fuel elements. Details of this study are contained in this report.
Date: December 15, 1960
Creator: Stringer, J. T. & Blanton, W. A.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation Monthly Activities Report: November 1960

Description: This is the monthly report for the Hanford Laboratories Operation, November 1960. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: December 15, 1960
Creator: Sale, W.
Partner: UNT Libraries Government Documents Department
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Liquid-Liquid Extraction With High-Molecular-Weight Amines

Description: A general review of the technique is given followed by a discussion of the principles involved, a survey of applications to various systems, and a collection of selected procedures associated with the technique which are reported in the literature. (J.R.D.)
Date: December 15, 1960
Creator: Moore, F. L.
Partner: UNT Libraries Government Documents Department
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Protection of Graphite by Impregnation. Quarterly Progress Report No. 3 for September 1-November 30, 1960. Vitro Job 2195

Description: The hypothesis that sample resistivity is the controlling factor in electrokinetic impregnation was substantiated. Experiments show that dense clay- bonded silicon carbide can be impregnated beneath the surface pores whereas only surface pore impregnation is achieved with both dense and porous graphite. The resistivity of the materials differ by a factor of about 1O/sup 10/. Although deep penetration of the substrate by the particles of the coating system is not achieved during deposition, there is evidence of considerable diffusion of the binder-carbide solid solution into the pores of the graphite after sintering. A number of sintered, crack-free, and adherent TaC coatings on ATJ graphite panels were prepared which showed evidence of surface pore penetration. The attainment of satisfactory reproducibility was difficult because of preferential deposition of the binder metal and contamination from erosion of the chrome-manganese steel ball mill. Efforts to prevent contamination by lining the mill with rubber were unsatisfactory. A silicon carbide liner for the mill was ordered and will be received in December. To prevent preferential deposition, precoating of the tantalum carbide particles with nickel by chemical precipitation and electroless nickel plating was investigated. Nickel coatings were obtained by both techniques; however, the chemically precipitated nickel was not adherent when the coated particles were placed in the electrophoretic bath. Good adherence was obtained by electroless plating; but this material, when sintered, cracked during the cooling cycle. Further investigation established that both iron and nickel are required as binders to obtain well-sintered Tar. Work was begun on the preparation of coated rocket nozzle liners for testing at NOL. Graphite nozzles were machined to the WM-D-800-2 configuration, and a cell was designed for obtaiining a uniform electrophoretic deposit. Test coatings were within the required thickness tolerance of plus or minus 0.002 in. The coatings, thus far, have cracked at …
Date: December 15, 1960
Creator: Ortner, M. H. & Klach, S. J.
Partner: UNT Libraries Government Documents Department
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Steady-State Tests of a Reactor Safety Device

Description: Introduction: This is the fourth report in a series of reports dealing in particular with a reactor safety device of a double diaphragm type.
Date: December 15, 1960
Creator: Springer, T. H.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation Monthly Activities Report: October 1960

Description: This is the monthly report for the Hanford Laboratories Operation, October 1960. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: November 15, 1960
Creator: Hanford Laboratories
Partner: UNT Libraries Government Documents Department
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Metallurgy of Zircaloy-2. Part I. The Effects of Fabrication Variables on the Anisotropy of Mechanical Properties

Description: The anisotropy of mechanical propertles of Zircaloy-2 was studied as a function of fabricatlon variables. The variatlon in tensile and impact properties with specimen orientation was taken as the measure of the anisotropy of mechanical properties for each material. A qualitative separatlon of the effects of the fabrication variables on the resulting anisotropy of mechanical properties is made, but it is valid only in the rolling plane of the plate. A contractile strain ratio, a ratio of the nataral contractile strain in the rolling plane to that in the direction normal to the rolling plane (measured on the round tensile specimen after testing), is introduced to aid in the interpretation of the tensile data. A Zircaloy-2 fabrication schedule (consisting of, in succession, ingot breakdown at a temperature of 1800 to 1900 gas-cooled F, major reduction at a temperature of 1800 to 1900 or 1350 to 1450 gas-cooled F, a to 1000 deg F. heat treatment of 1800 to 1850 gas- cooled F for 30 min, followed by either a water-quench or a rapid aircool to below 1200 gas-cooled F, a final reduction of 25 to 40% at l000 gas-cooled F, and an anneal at 1400 to 1425 gas-cooled F for 30 min) was found to produce a much more nearly isotropic material than any of the schedules investigated. This material is anisotropic in strain behavior and tensile properties in comparison to the common cubic materials. The elimination of the intermediate to 1000 deg F. heat treatment from the fabrication schedule resulted in the production of a material with tensile properties for all directions in the plane of rolling essentially the same, but which allowed little cortractile strain to occur in the thickness direction of the plate. This indicated that a high degree of three-dimensional anisotropy existed in the material. The …
Date: November 15, 1960
Creator: Rittenhouse, P.L. & Picklesimer, M.L.
Partner: UNT Libraries Government Documents Department
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Optimization of K Reactor power levels related to a zirconium tube replacement project

Description: The assumption of tube replacement losses can have a significant effect in the determination of optimum power levels and goal exposures. The tube replacement loss term in the reactor process optimization model is based on calculating the average projected tube replacement losses that will result from operation at given power and temperature conditions. Tube replacement losses associated with external corrosion, Van Stone flange failure, etc. (i.e., basically non-power level-temperature dependent) are assumed to be miscellaneous losses and are not included in the tube replacement term. Over a period of several years the experienced tube replacement losses (due to internal corrosion) should compare reasonably well with the losses predicted by the optimization model. Planned tube replacement project action which would require, in some cases, premature tube removal is a special situation which requires a modified approach to the prediction of tube replacement losses and to the optimization of reactor power levels prior to project action. A method has been developed for optimizing reactor power levels and goal exposures based on any assumed calendar date for major tube replacement project action. It is the purpose of this document to discuss the general application of this method in the optimization and illustrate the method by presenting specific application of the method to the K Reactors.
Date: November 15, 1960
Creator: Fuller, N. E. & Graves, S. M.
Partner: UNT Libraries Government Documents Department
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PRESSURE AND TEMPERATURE INSTRUMENTATION FOR DYNAMIC MEASUREMENTS IN THE KEWB PROGRAM. A Summary Report

Description: After an experimental survey of eight different models of pressure transducers, a system with fast response was developed to measure pressures in the KEWB reactor. The transducers used in the system operate in an environment which presents a high radiation level but which has temperatures that are quite low for a reactor. Thus they would not be suitable for use in a power reactor because of the temperature limitation. Since installation of this pressuremeasuring system in the KEWB reactor, the recombiner tests and transient experiments have been completed, and observations have been made of explosion pressures. Two very useful pieces of special equipment were developed in the course of this project. One was the remotely controlled shock tube, which was used for testing transducers and was operable in the reactor through-tube. The other was the dual DADEE circuit developed to compensate for ringing and insufficiently fast response in transducers with two degrees of freedom. (auth)
Date: November 15, 1960
Creator: Harris, S.P. & Bumpus, C.F. Jr.
Partner: UNT Libraries Government Documents Department
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SYNTHESIS AND FABRICATION OF REFRACTORY URANIUM COMPOUNDS. Quarterly Report No. 5, August 1 through October 31, 1960

Description: Additional quantities of UC, UN, and U/sub 3/Si/sup 2/ were prepared to be used in fabrication of test specimens for property determinations. A reduction in oxygen contamination of UN and U/sub 3/Si/sup 2/as achieved by improved techniques of synthesis.>s Preliminary values for thermal expansion, modulus of elasticity, and corrosion in boiling water were also obtained for these materials. (For preceding period see TID-6591.) (J.R.D.)
Date: November 15, 1960
Creator: Taylor, K. M. & McMurtry, C. H.
Partner: UNT Libraries Government Documents Department
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ABWR: PL-2 Design Report

Description: From preface: This report satisfies the quarterly progress report requirements for PL-1 and PL-2 plant design work for the period ending September 30, 1960 At present time a SL-1 Core 2 is under construction. This is a replacement core for SL-1 (ALPR) and will be identical to a PL-2 core; a PL condenser is under test at the SL-1 facility; final construction plans for PL components and modules which are not site sensitive will be completed in March 1961.
Date: October 15, 1960
Creator: Combustion Engineering, inc. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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Compatibility of SNAP Fuel and Clad Materials

Description: Samples capsules containing buttons of materials of interest for SNAP fuel elements were held at temperatures up to 1600°F , in hydrogen, under a 20-tsi load for 200+ hours.
Date: October 15, 1960
Creator: Balkwill, J.K.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation Monthly Activities Report: September 1960

Description: This is the monthly report for the Hanford Laboratories Operation, October, 1960. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: October 15, 1960
Partner: UNT Libraries Government Documents Department
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A Study of Sodium Fires

Description: A study of sodium fires was performed to obtain detailed information on their characteristics and behavior in order to develop techniques for preventing, containing, and combatting them. lnvestigation was made of the technology of sodium fires, design criteria for improving the fire resistance of equipment and installations using sodium as a coolant, extinguishing materials and procedures for fighting sodium fires, and the evaluation of protective equipment. (auth)
Date: October 15, 1960
Creator: Gracie, J.D. & Droher, J.J.
Partner: UNT Libraries Government Documents Department
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An appraisal of the Hanford high-level waste program

Description: As set forth in the CPD Waste Management Program (HW-63958), new and improved methods of waste processing are planned to be initiated at Hanford. A major part of this program is concerned with the high-level wastes from the Purex Plant, with major objectives being the control of long-term hazards, the insurance of production continuity, and the attainment of positive waste accountability at reasonable over-all costs. Specific plans for the disposal of Purex wastes are based on the use of high temperature calcination for immobilization and volume reduction of the solvent extraction raffinates (1WW). Four major steps are involved, each of which is of basic importance to the program objectives. These are: (1) interim 1WW storage and removal for calcination, (2) calcination, (3) primary containment of the calcined waste, and (4) long-term storage. Immobilization of coating wastes and organic wash wastes is also planned, either by tank solidification methods or possibly by inclusion in the calcination feed stream. This document was dated September 15, 1960.
Date: September 15, 1960
Creator: Campbell, B. F.
Partner: UNT Libraries Government Documents Department
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