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Braze Alloys v.s. Atmospheres : Final Report Project 1325
Summary. At the time this project was initiated, all brazing had been confined to small retorts of ten cubic feet capacity or less. Larger assemblies were scheduled which required retorts of over 100 cubic feet capacity. Hydrogen atmospheres had given the best results, however, there was considerable reluctance to use hydrogen in these large retorts from a safety standpoint. It was thought that thru the use of PMC 2252, an argon - 2 1/2% hydrogen gas atmosphere which in non-explosive, sufficient cleaning action might be attoined without the inherent hazards encountered with hydrogen. An investigation of the argon - 2 1/2% hydrogen gas as a brazing atomosphoer
Date:
May 21, 1959
Creator:
Rogers, S. L.
Object Type:
Report
System:
The UNT Digital Library
The Effect of Solution and Vessel Thermal Expansion on Volume Measurements in the Chemical Processing Department
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 and certain aspects of temperature considerations in the volume determinations. However, there is a need to document for future reference the consideration given temperature and provide at the same time information which covers the temperature angle on all volume methods used in the Chemical Processing Department.
Date:
May 22, 1959
Creator:
Johnson, W. R.
Object Type:
Report
System:
The UNT Digital Library
Report of Fire in Laboratory Hood, Wing I, Building 4500
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.
Object Type:
Report
System:
The UNT Digital Library
Artificial Cooling of the Columbia River By Dam Regulation Part 1
In early July, 1958, it appeared that Columbia River temperature at HAPO would be near 24.5ºC by the end of August. River temperature were averaging 4º to 5º above 1957 figures and were 3º to 4º above the ten year highs. It seemed desirable to examine the problem to determine if any corrective measure could be taken, since it was apparent that production losses were imminent.
Date:
May 25, 1959
Creator:
Kramer, H. A.
Object Type:
Report
System:
The UNT Digital Library
Brief Review of Heat Transfer Problems Encountered in the Production of Magnetic Fields
The design of internally cooled electrical coils for the production of high frequency intensity magnetic fields presents many new aspects and combinations of the familiar modes of heat transfer. However, the customary methodology appears to be sufficient for preliminary analysis and understanding of those problems. This methodology comprises the derivation of a qualitative, approximate equation expressing the relative performance of the various parts of a system, followed by an examination of this equation in order to locate the limiting features of the system. These features are then investigated by more powerful methods, which in turn provide guidance for development research in the laboratory.
Date:
May 25, 1959
Creator:
Alexander, L. G.
Object Type:
Report
System:
The UNT Digital Library
Design Criteria for a Pile Oscillator
In the use of a reactor as a device to measure neutron cross sections, the pile oscillator is often employed because of its much higher sensitivity compared to that available in static reactivity measurements. The factor limiting the available in static reactivity measurements. The factor limiting the available sensitivity is the generation of random noise, which originates in the statistical nature of the chain reaction. In other words, the nuclear reactions which maintain the chain reaction do not proceed uniformly, but rather at rates which fluctuate in time around some average values. These fluctuations limit the accuracy of measurements in the reactor.
Date:
May 25, 1959
Creator:
Dresner, Lawrence
Object Type:
Report
System:
The UNT Digital Library
Hastelloy F Dissolver Installation in 321 Building
Hastelloy F is a prime contender as a material of construction for plant dissolvers in the power fuel reprocessing program. Consequently, the fabrication and installation of dissolver was undertaken to delineate any unknown problems associated with the use of Hastelloy F; and, at the same time, to provide a vessel for development studies on the Niflex or the Sulfex processes. The purpose of this report is to describe the actual basis for design as well as to present the problems encountered during the fabrication of the vessels.
Date:
May 25, 1959
Creator:
Cooley, C. R.
Object Type:
Report
System:
The UNT Digital Library
Measurement of the Nuclear Materials Content of Non-Production Fuels
In considering the problems associated with the measurement of SSNM content of Non-Production Fuels, two distinct problems are apparent. The first is the technical problem of obtaining highly accurate measurements in a complicated chemical and physical system. The second is the administrative problem of choosing a measurement system which provides a basic of financial settlement acceptable to both the seller (reactor operator) and the buyer (Commission).
Date:
May 25, 1959
Creator:
Schneider, R. A.
Object Type:
Report
System:
The UNT Digital Library
Radial Thermal Flux Traverses in Natural Uranium - Graphite Lattices
The spatial distribution of thermal neutrons in a reactor lattices cell is of fundamental importance for many reasons. First of all, this information allows the determination of the relative absorption rates in each component of the cell which in turn enables a determination of the thermal utilization, and the diffusion length of the lattice. In addition, the observed spatial distributions of thermal neutrons in the lattice cell is of major interest in testing various approximations to the solution of the transport equation such as the P1 and P3 solutions.
Date:
May 25, 1959
Creator:
Nilson, R. & Oakes, T. J.
Object Type:
Report
System:
The UNT Digital Library
The Development of a Fluidized Bed Reactor for the Fluorox Process: Unit operations Monthly Status Reports for the Period November, 1958, Through May, 1959
Results of four experiemental runs in the Fluorox fluidized bed reactor system are reported. The engineering feasibility of UF6 production from UF4 by use of dry air of O2, 2UF4 + O2 = UF6 + UO2F2, in an Inconel fluidized bed reactor at 800-850°C was demonstrated in two experimental tests in which greater than 90% of the theoretical amount of UF6 was collected or measured. Two runs made with crude UF4 (produced from unpurified mill concentrate) as the feed material, showed that UF6 could be produced at 700-725°C but corrosion on Inconel was prohibitive.
Date:
May 26, 1959
Creator:
Bresee, J. C.; Scott, C. D. & Horton, R. W.
Object Type:
Report
System:
The UNT Digital Library
Sizes of U. S. Steam- Electric Plants
At the present time, plants in the 100-500Mv size range are more numerous and carry the greatest portion (over 50%) of the total steam-electric plant load in the U.S. utilities industry. The contribution of plants of over 1,000-Mv capacity is increasing more rapidly than any other size clarification and at present represents about 10% of the total capacity. By 1962 the TVA will have six plants with capacities of over 1,000-Mv. The largest steam-electric plant in the U.S. is the TVA plant at Kingston, Tenn., with a nameplate capacity of 1,440-Mv. Turbine-generator units are also following a trend of ever-increasing size. In present construction, the 150-200 Mv size range for units is the most common and represents the greatest contribution to capacity. Two units of 500-Mv nameplate rating each, the largest in the U.S., are on order by the TVA, and an 800 Mv unit is contemplated.
Date:
May 26, 1959
Creator:
Robertson, R. C.
Object Type:
Report
System:
The UNT Digital Library
Problems in Accountability Measurements Associated with the Interim Chemical Processing Program
Available knowledge of precision limits in S.S. accountability measurements and/or calculations by reactor and chemical processing groups is surveyed and summarizes. Experience in comparisons of reactor (production and research) calculations versus chemical plant accountability measurements is also reported. A general tentative conclusion is that available precisions (+/- 0.54 to +/- 0.78% ) in chemical plant measurements is also reported. A general tentative conclusion is that available precisions (+/- 1.0 to +/- 11.0%) possible by calculations (nuclear and/or engineering) of power reactor systems; however, with operation and empirical experience (e.g. less than +/-1.0%
Date:
May 28, 1959
Creator:
Arnold, E. D. & Gresky, A. T.
Object Type:
Report
System:
The UNT Digital Library
Toy Top Plasma Injector
Introduction: "It is the purpose of this note to describe the construction and operation of the plasma injectors used in the magnetic high compression experiments in progress at the Lawrence Radiation Laboratory at Livermore. As the investigations of these injections is still in progress, remarks concerning their operation or the characteristics of the injected plasma are of a tentative nature."
Date:
May 28, 1959
Creator:
Coensgen, F. H.; Cummins, W. & Sherman, A.
Object Type:
Report
System:
The UNT Digital Library
Volatility: Fluorinator Design FV-100, Zr-U Fuel Element Processing Phase
Volstility Pilot Plant Mark III Fluorinator will be a double-chamber type vessel, each chamber 2-1/2ft. by 16in. o.d. separated by a 5 in. pipe 15 in. long. ASME flanged and dished heads will be used for the chamber tops and conical sections with a 60º apex angle for the chamber bottoms. A new furnace designed to maintain the complete lower chamber (molten salt + freeboard) above melt temperature will eliminate past experiences of salt solidification on the wall, heads, and in or on the internal process lines. External pipe runs will be sutoresistance heated to allow melting and drain back of salt plugs. The upper chamber serves as a gas de-entrainment and solids precipitation device to retain most of the entrained salt and condensable fluorides in the 100-400°C temperature range.
Date:
May 28, 1959
Creator:
Ruch, J. B.
Object Type:
Report
System:
The UNT Digital Library
Electron-Electron Coincidence Spectrometer BRS-IV
This report summarizes the original construction and recent modifications of the electron-electron coincidence spectrometer BRS-IV located in Building 70 of the Lawrence Radiation Laboratory. In addition to new information on the modified spectrometer, this report also contains a large amount of material taken from two previous UCRL reports.
Date:
May 1960
Creator:
Unik, John P.
Object Type:
Report
System:
The UNT Digital Library
Hazards Summary Report for the Army Package Power Reactor : SM-1, Task XVII
Preface. This technical report is an updated and revised version of the original SM-1 (APPR-1) Hazards Summary Report. The original report was issued July 1955, almost two years before construction of the SM-1 plant was completed. During that time interval there were numerous design changes. Consequently, the original report does not accurately describe the plant as built. This revision is written after the SM-1 has been operated 3 years. It describes the as-build plant and includes plant modifications and experience obtained during the first 3 years of SM-1 operation.
Date:
May 1960
Creator:
Rosen, S. S.
Object Type:
Report
System:
The UNT Digital Library
Hindrance Factors For Alpha Decay
The theoretical half lives for alpha emissions have been calculated for nearly all of the complex alpha spectra. The spin independent equations of Preston were used for the calculations. The nuclear radius for the even-even nuclei was determined with the assumption that the alpha transition to the ground state is unhindered. For odd mass nuclides the average of the nuclear radii of the adjacent even-even nuclides was used. For odd-odd nuclides the average of the nuclear radii of the adjacent odd mass nuclides of the same atomic number was used.
Date:
May 1960
Creator:
Michel, Helen V.
Object Type:
Report
System:
The UNT Digital Library
Project Hobo : Shear and Compressional Velocity Measurements
Abstract. Three groups of 100 foot holes were drilled vertically downward from the floor of U 12e main tunnel and U 123.03 drift at the Nevada Test Site. Distances between holes in each group varied from 13 to 375 feet. One hole in each group was used a a 'shot hole'; the others for seismometers to records the energy generated in the 'shot hole'. Two types of recordings were made. One for dilatational or longitudinal "P" waves and one for transverse or shear "S" waves. Simultaneous recordings were made on photographic paper and on magnetic belts with a minimum of three "specimen" records at each hole, for each type of recording. The magnetic belts were transcribed to 1/2 inch IRIG tape for computer use. Rock density measurements were also made in the holes. From these data Poisson's Ratio, Bulk Modulus, Rigidity Modulus, and Young's Modulus were computed. Elastic constant values obtained 'in sltu' are much higher than those determined by soils laboratory tests on small rock samples. The data obtained are considered to be of exceptionally high accuracy.
Date:
May 1960
Creator:
Swain, R. J.; Heald, C. L. & Snodgrass, D. T.
Object Type:
Report
System:
The UNT Digital Library
Radium and Mesothorium Poisoning and Dosimetry and Instrumentation Techniques in Applied Radioactivity
"The study of the toxicity of Ra and MsTh(Ra/sup 228/) in humans was continued. Several Thorotrast cases were also examined. Physical and clinical studies were made on 151 persons. In all cases possible gamma ray measurements were made of Ra and MsTh decay products retained in the body, alpha -ray measurements of Rn and Rn/sup 220/ in breath, a complete medical history was taken, a complete x-ray examination was made of the skeleton, and urinalysis, hematological, and blood chemistry studies were made."
Date:
May 1960
Creator:
Evans, Robley D.
Object Type:
Report
System:
The UNT Digital Library
Scale "Up or Down" Analysis for Prototype Test
Introduction: In conjunction with the final design and development of a 70 MW sodium intermediate heat exchanger and a sodium steam generator, an analysis is required which can be used as a basis for a determination to scale up or scale down the designs. Included in this analysis are those considerations leading to the recommendation of the best prototype test unit and to some of the limits imposed on scaling up or down when considering future applications of designs other than those actually tested. In addition, these considerations include aspects required to accurately predict the performance, operation, mechanical reliability, and feasibility of fabrication of the 70 MW design.
Date:
May 1, 1960
Creator:
Alco Products (Firm).
Object Type:
Report
System:
The UNT Digital Library
Project Hobo : Densities and Velocities Measured on Specimens from Instrument and Shot Holes
Abstracts. Results are given for bulk-density and pulse-velocity measurements performed on specimens of the Project Hobo medium. Test techniques, sample handling, and specimen preparation are described. Values are tabulated in terms of sample origin and geological identity.
Date:
May 2, 1960
Creator:
Guido, Raymond S. & Warner, Stanley E.
Object Type:
Report
System:
The UNT Digital Library
A Miniature Beta Scintillation Detector
The development of a miniature probe was desired for measuring approximate single nuclide beta dose rate in solution and in various animal organs. This probe designed for biological experiments, was to have maximum possible sensitivity to detect low levels of nuclide concentrations. The desired dimensions of the light pipe were to be approximately one-fourth-inch diameter with lengths of three to twelve inches.
Date:
May 4, 1960
Creator:
Kent, R. A. R. & Sheen, E. M.
Object Type:
Report
System:
The UNT Digital Library
Redox Dissolver Off-Gas Monitor, Calibration and Test
In order to prevent dangerous concentrations of combustible gases such as hydrogen and ammonia in Redox dissolvers, a continuous analysis of the off-gases is needed. Hydrogen is evolved from most fuel element dissolution processes now used or planned for use at Redox. Ammonia is also released from ammonium fluoride dissolution of zirconium and caustic dissolution of aluminum cladding. Oxides of nitrogen and hydrogen are formed during nitric acid dissolution of uranium or plutonium-aluminum alloys. Since no fixed ratio exists between the concentrations of any two of these gases, the determination of combustible gases in complex mixtures is not possible with a single bulk property analyzer.
Date:
May 4, 1960
Creator:
Huck, C. E.
Object Type:
Report
System:
The UNT Digital Library
Aluminum Alloy Work at Hanford
Investigation of aqueous and steam corrosion at elevated temperature has been carried on at Hanford for several tears. A number of reports have been published on various phases of the corrosion program but, except for monthly reports, little has been written on the progress of the Corrosion and Coatings Operation alloy development program. This interim report will outline the more important current phases of the aluminum alloy program.
Date:
May 6, 1960
Creator:
Bowen, H. C.
Object Type:
Report
System:
The UNT Digital Library