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- Chemical Engineering Division Basic Energy Sciences Research: July 1976-September 1977
- Studies in basic energy science covered many different activities, nearly all of which were designed to gain information required for a better understanding of systems important to national needs in energy and environment. Studies of associating gases included measurements of thermal conductivities and basic molecular orbital calculations. Raman spectroscopy and spectrophotometry were used to determine thermodynamic and spectroscopic data on salt vapor complexes. Polarized Raman spectra of As2S3 thin films and vapors were recorded. Halogenation of lanthanide oxides with aluminum chloride allowed the separation of the resultant chloride complexes by vapor transport. Electrochemical titrations were used to obtain the solubility product of iron sulfide in molten LiCl-KCl eutectic. Solubility products of eleven sulfides in the same eutectic mixture were calculated. Galvanostatic techniques were used to study metal deposition/dissolution reactions in molten salts. Activity coefficients of lithium in lithium-lead alloys were determined electrochemically; phase diagrams of ternary alloys of Li-Al-Mg and Li-Ca-Mg were computed. Thermodynamic studies are being made of the sorption of hydrogen by Li-Al and Li-Pb alloys. The study of the solubility of oxygen in liquid lithium was completed. An electric resistance method for measuring distribution properties of nonmetallic elements in binary metallic systems containing lithium is being developed. Calorimetric methods were used to measure standard enthalpies of formation of some coal components, lanthanum and rare earth trifluorides, and gamma-UO3, UF6, Cs3CrO4, Cs4CrO4, As4S4, and As2S3. High-temperature enthalpy increments were measured for LaF3 and beta-As4S4. The acidities of airborne ammonium sulfate-bearing particles from various areas of the U.S. were measured using Fourier-transform infrared spectroscopy.
- Chemical Engineering Division Environmental Chemistry Annual Report: July 1975-June 1976
- The chemistry of airborne particulate matter is being investigated by means of laboratory and field studies. Experiments were conducted using the flow reactor to identify the reaction conditions under which detectable amounts of sulfate particles could be formed under gaseous sulfur dioxide. A procedure was developed for the analysis of acidic and neutral ammonium sulfate in filter-collected samples of atmospheric particulate matter.
- Chemical Engineering Division Fast-Neutron Dosimetry, Annual Report: July 1975-June 1976
- One of the objectives of the Dosimetry and Damage Analysis Center is to provide standardized dosimetry technology for materials-study programs within the ERDA Division of Magnetic Fusion Energy. Current efforts have included characterization of neutron environments in terms of fluence and spectral distribution for materials experiments conducted at the Lawrence Livermore Laboratory's (LLL) Rotating Target Neutron Source and at the LLL-Davis Cyclograaff. Environment characterization efforts at Brookhaven National Laboratory's High Flux Beam Reactor and those pertaining to an enriched-uranium converter for the ANL CP-5 reactor are also described. The capability of calculating material radiation damage parameters associated with these neutron environments is demonstrated. Average fission yields determined from two fast-neutron irradiations and one thermal-neutron irradiation are compiled for laboratories participating in the inter-laboratory Reaction Rate program. These results are in excellent agreement with literature values. Progress on the development of boron-10 and lithium-6-loaded liquid scintillation detectors for detecting very low intensity neutrons is presented. Material purification tests and performance tests of scintillation mixtures are described.
- Chemical Engineering Division Fuel Cycle Programs October-December 1976
- Report on fuel-cycle studies including pyrochemical separation of plutonium and americium oxides from contaminated materials of construction such as steel.
- Chemical Engineering Division Fuel Cycle Programs Progress Report: April-June 1978
- Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research. This report includes studies on advanced solvent extraction techniques focused on the development of centrifugal contactors for use in Purex processes, extraction kinetics of ruthenium and zirconium in the presence of uranium, and dispersion of uranium and plutonium by fires.
- Chemical Engineering Division Fuels and Materials Chemistry Annual Report: July 1975-June 1976
- Annual report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.
- Chemical Engineering Division Physical Inorganic Chemistry Annual Report: July 1975-June 1976
- Various aspects of physical inorganic chemistry were investigated and are summarized in this report.
- Chemical Engineering Division Reactor Fuels and Materials Chemistry Research: July 1976-September 1977
- Report describing the research and development activities related to reactor fuels and fast-reactor programs conducted by the Argonne National Laboratory Chemical Engineering Division.
- Chemical Engineering Division Reactor Safety and Physical Properties Studies Annual Report, July 1975-June 1976
- A report of the work on Reactor Safety and Physical Property Studies performed in the Chemical Engineering Division at Argonne National Laboratory is given for the period July 1975-June 1976.
- Chemical Engineering Division Research Highlights
- Report on electrochemical energy development, including development of advanced, high-temperature lithium/metal sulfide batteries for vehicle propulsion and stationary energy storage.
- Chemical Engineering Division Research Highlights 1978
- Report of activities at Argonne Chemical Engineering Division, including lithium/metal sulfide batteries, electro-chemical project management, advanced fuel cell development, utilization of coal, magnetohydrodynamics, solar energy, fast reactor chemistry, and fuel cycles.
- Chemical Engineering Division Research Highlights 1979
- Report of activities of Argonne Chemical Engineering Division, including advanced battery project, electro-chemical project management, advanced fuel cell development, utilization of coal, magnetohydrodynamics heat and seed recovery technology, solar energy, fast reactor chemistry research, nuclear fuel cycle studies, magnetic fusion energy research, and basic energy science.
- Chemical Engineering Division Sodium Technology Annual Report: July 1975-June 1976
- The Sodium Technology program currently comprises three parts. The first part is aimed at developing a model for accurately describing the behavior of tritium in LMFBRs from its formation in the core to its ultimate retention in the cold traps or release to the environment. Two important parts of this model are the behavior of the sodium cold traps and permeation of tritium through the steam-generator heat-transfer surfaces. A tritium monitor has been developed and installed on EBR-II to measure tritium specific activities and to test the model of an operating LMFBR. The second part of the program is focused in two areas: 91) on-reactor-site conversion of commercial-grade sodium and (2) requalifying sodium from decommissioned reactors for reuse in future LMFBRs.
- Chemical Engineering Division Summary Report
- Measurement of radioactive carry-over was made on borax III operating at 300 psig and at power levels ranging from 4 to 14 mv. Decontamination factors of from 1.5 x 104 (at 14 mv) were obtained. These data are in essential agreement with those predicted by previous laboratory experimental work.
- Chemical Engineering Division Summary Report for January, February, and March 1957
- A fused fluoride process for dissolution of zirconium-uranium fuel alloys is being developed. The alloy is dissolved in an equimolar sodium fluoride-zirconium fluoride melt at 600°C by sparging the system with hydrogen fluoride. The uranium is volatilized from the melt as the hexafluoride by a sparging operation with fluorine or bromine pentafluoride vapor. This product is then decontaminated and purified by fractional distillation.
- Chemical Engineering Division Summary Report for January, February, and March 1958
- Development work was continued on the fused fluoride process for the recovery of enriched uranium from zirconium-matrix fuel alloys. The alloy is dissolved by immersing it in molten sodium fluoride-zirconium fluoride at 600°C and passing hydrogen fluoride vapor through the system.The dissolved uranium tetrafluoride in the melt is then volatilized as uranium hexafluoride by sparging with fluorine. The uranium hexafluoride product is purified and decontaminated by fractional distillation. Additional corrosion tests were made on a variety of metals in an effort to find a material of construction suitable for the fluorination step. All the metals tested, with the exception of Hastelloy B, were attacked rapidly in the fluorinated melt. The attack was particularly severe at the melt-gas interface when tests were made with partially submerged specimens of the metals.
- Chemical Engineering Division Summary Report : January, February, And March 1953
- Dissolution of the large number of samples obtained from the natural uranium blanket of the Experimental Breeder Reactor after approximately 485,000 kw.-hr. of operation has been completed, and analysis of these samples for uranium consumed and plutonium formed is well along. An attempt is being made to distinguish quantitatively between uranium-238 and uranium-235 fission in the blanket area by determining the ratio of ruthenium-106 to cesium-137 in the fission products.
- Chemical Engineering Division Summary Report January, February, and March, 1954
- Progress is reported on (1) direct cycle boiling reactor studies, (2) solvent extraction, (3) fluoride volatilization separation process, (4) elevated temperature separations, (5) fluidization studies, (6) development of analytical techniques, (7) processing and utilization of radioactive wastes.
- Chemical Engineering Division Summary Report July, August, and September, 1956
- Additional runs have been made in the six-inch, continuous-flow mixing chamber to study the rate of mass transfer between isobutanol and water. These runs were inconclusive because the effluents were mutually saturated. A new four-inch cell has been designed and is being fabricated; this will permit a reduction in the time available for mass transfer. Consideration has been given to other liquid pairs which may transfer more slowly than isobutanol-water. The system nitrobenzene-ethylene glycol appears attractive.
- Chemical Engineering Division Summary Report July, August, and September, 1957
- Development work continued on a fused salt process for the recovery of uranium from zirconium-matrix fuel alloys. The fuel is dissolved in a sodium fluoride-zirconium fluoride melt at 600°C by hydrogen fluoride sparging. The melt is then sparged with fluorine gas which volatilizes the dissolved uranium as the hexafluoride. The final decontamination and purification of the uranium hexafluoride are accomplished by fractional distillation. The testing of graphite as a container material for the hydrofluorination step was continued. Additional thermal cycling experiments were performed, using a helium sparge in equimolar sodium fluoride-zirconium fluoride melt at 600°C. The extent of penetration of the fused salt into the graphite was determined. No mechanical degradation was present. Dimensional change data were also obtained for graphite vessels in which the fused salt was sparged with hydrogen fluoride.
- Chemical Engineering Division Summary Report October, November, and December, 1953
- Progress is reported on (1) experimental breeder reactor program, (2) solvent extraction, (3) fluoride volatilization separation process, (4) elevated temperature separations, (5) denitration of uranyl nitrate in a fluidized bed, (6) development of analytical techniques, (7) processing and utilization of radioactive wastes.
- Chemical Engineering Division Summary Report October, November, and December, 1956
- A final series of runs was made in a four-inch continuous-flow mixing chamber to study the transfer of isobutanol into water and nitrobenzene into ethylene glycol. Satisfactory techniques were developed to provide for the rapid analysis of these systems. In addition, a light-scattering correlation was prepared to provide a measure of the interfacial area of the yellow-colored nitrobenzene-ethylene glycol mixtures.
- Chemical Engineering Division Thermochemical Studies Annual Report: July 1975-June 1976
- Standard enthalpies of formation at 298.15 K are reported for MgUO4, CaUO4, BaUO4, VF3, and PrF3 based on solution and fluorine bomb calorimetric measurements. High-temperature enthalpy increments have been determined for MgUO4 by drop calorimetry. Preliminary work on gamma -UO3 and beta-LiAl is described.
- Chemical Technology Division Annual Technical Report 1985
- Highlights of the Chemical Technology (CMT) Division's activities during 1985 are presented. In this period, CMT conducted research and development in areas that include advanced batteries--mainly lithium-alloy/metal sulfide and sodium/sulfur, advanced fuel cells with molten carbonate or solid oxide electrolytes, corrosion-protective coatings for high-strength steel, coal utilization, including the heat and seed recovery technology for coal-fired magnetohydrodynamics plants and the technology for fluidized-bed combustion, methodologies for recovery of energy from municipal waste nuclear technology related to waste management, the recovery processes for discharged fuel and the uranium blanket in a sodium-cooled fast reactor, and proof of breeding in a light water breeder reactor, and physical chemistry of selected materials in environments simulating those of fission and fusion energy systems.
- Chemical Technology Division Annual Technical Report: 1986
- Annual report of Argonne National Laboratory's Chemical Technology (CMT) Division. In this period, CMT conducted research and development in areas that include the following: (1) high-performance batteries--mainly lithium-alloy/metal sulfide and sodium/sulfur; (2) aqueous batteries (lead-acid, nickel/iron, etc.); (3)advanced fuel cells with molten carbonate or solid oxide electrolytes; (4) coal utilization, (5) methods for recovery of energy from municipal waste; (6) methods for the electromagnetic continuous casting of steel sheet; (7) techniques for treatment of hazardous waste such as reactive metals and trichloroethylenes; (8) nuclear technology related to waste management.
- Chemical Technology Division Annual Technical Report 1988
- Highlights of the Chemical Technology (CMT) Division's activities during 1988 are presented. In this period, CMT conducted research and development in the following areas: (1) high-performance batteries (mainly lithium-alloy/metal sulfide, sodium/metal chloride, and sodium/sulfur); (2) aqueous batteries (lead-acid, nickel/iron, etc.); (3) advanced fuel cells with molten carbonate or solid oxide electrolytes; (4) coal utilization, including the heat and seed recovery technology for coal-fired magnetohydrodynamics plants and the technology for fluidized bed combustion; (5) methods for recovery of energy from municipal waste and techniques for treatment of hazardous chemical waste; (6) nuclear technology related to a process for separating and recovering. transuranic elements from nuclear waste and for producing 99Mo from low-enriched uranium targets, the recovery processes for discharged fuel and the uranium blanket in a sodium-cooled fast reactor, and waste management; and (7) physical chemistry of selected materials in environments simulating those of fission and fusion energy systems.
- Chemical Technology Division Annual Technical Report: 1991
- Annual report of the Argonne National Laboratory Chemical Technology Division (CMT) discussing the group's activities during 1991. These included electrochemical technology; fossil fuel research; hazardous waste research; nuclear waste programs; separation science and technology; integral fast reactor pyrochemical processes; actinite recovery; applied physical chemistry; basic chemistry research; analytical chemistry; research and development; and computer applications.
- Chemical Technology Division Annual Technical Report: 1992
- Annual report of the Argonne National Laboratory Chemical Technology Division (CMT) discussing the group's activities during 1992. These included electrochemical technology; fossil fuel research; hazardous waste research; nuclear waste programs; separation science and technology; integral fast reactor pyrochemical processes; actinide recovery; applied physical chemistry; basic chemistry research; analytical chemistry; applied research and development; and computer applications.
- Chemical Technology Division Annual Technical Report: 1993
- Annual report of the Argonne National Laboratory Chemical Technology Division (CMT) discussing the group's activities during 1992. These included electrochemical technology; fossil fuel research; hazardous waste research; nuclear waste programs; separation science and technology; integral fast reactor pyrochemical processes; actinide recovery; applied physical chemistry; basic chemistry research; and analytical chemistry.
- Chemical Technology Division Annual Technical Report: 1994
- Annual report of the Argonne National Laboratory Chemical Technology Division (CMT) discussing the group's activities during 1994. These included electrochemical technology; fossil energy research; hazardous waste research; nuclear waste programs; separation science and technology; electrometallurgical technology; actinide recovery; applied physical chemistry; basic chemistry research; analytical chemistry.
- Chemical Technology Division Annual Technical Report for 1984
- Report on studies of advanced batteries, aqueous batteries, advanced fuel cells, coal utilization, methodologies for recovery of energy from municipal waste, solid and liquid desiccants, nuclear technology related to waste management, and physical chemistry of selected materials in environments simulating those of fission, fusion, and other energy systems.
- Chemistry Division, Section C-1, Quarterly Report July, August, and September 1952
- Report describing the research and development activities related to nuclear chemistry and radiochemistry and basic chemistry conducted by the Argonne National Laboratory Chemistry Division, Section C-1.
- Chemistry Division Section C-1 Quarterly Report, October, November, And December 1952
- Report describing the research and development activities related to nuclear chemistry and radiochemistry and basic chemistry conducted by the Argonne National Laboratory Chemistry Division, Section C-1.
- Chemistry Division, Section C-1, Summary Report for April, May, And June 1952
- Report describing the research and development activities related to nuclear chemistry and radiochemistry and basic chemistry conducted by the Argonne National Laboratory Chemistry Division, Section C-1.
- Chemistry Division, Section C-1, Summary Report For October, November and December 1951
- Report describing the research and development activities related to nuclear chemistry and radiochemistry and basic chemistry conducted by the Argonne National Laboratory Chemistry Division, Section C-1.
- Chemistry Division, Section C-II, Summary Report For April, May, And June 1952
- This report was written by different scientist on various experiments of solid state, physical chemistry, radiochemistry and analytical, and special problems.
- Chemistry Division, Section C-II, Summary Report for July, August, and September 1952
- This report deals with the (1.1) physical properties of graphite, (1.2) effects of pile irradiation on the properties of graphite, (1.3) effect of irradiation on "ceramic" materials, (1.4) effects of radiation on ice -- the x-ray induced luminescence of ice, (1.5) investigation of color centers and other optical properties of single crystals. (2.1) radiation chemistry of liquids, (2.2) application of mass spectrometry to chemical problems, (2.3) vapor pressure and heat of vaporization of uranium, (3.1) nuclear properties of Zr93 and Nb93m from fission, (3.2) mass distribution in the spontaneous fission of Cm242, (3.3) Upper limit to the lifetimes of the first excited states of Th236, U234, and Pu236, (3.4) on the one-body model of alpha radioactivity, (4.1) spectrographic analysis, (4.2) chemical analysis, (5.1) paramagnetic resonance measurements, and (5.2) the 60-inch cyclotron.
- Chemistry Division, Section C-II, Summary Report for July, August, and September 1952
- This report deals with the (1.1) physical properties of graphite, (1.2) effects of pile irradiation on the properties of graphite, (1.3) effect of irradiation on "ceramic" materials, (1.4) effects of radiation on ice -- the x-ray induced luminescence of ice, (1.5) investigation of color centers and other optical properties of single crystals. (2.1) radiation chemistry of liquids, (2.2) application of mass spectrometry to chemical problems, (2.3) vapor pressure and heat of vaporization of uranium, (3.1) nuclear properties of Zr93 and Nb93m from fission, (3.2) mass distribution in the spontaneous fission of Cm242, (3.3) Upper limit to the lifetimes of the first excited states of Th236, U234, and Pu236, (3.4) on the one-body model of alpha radioactivity, (4.1) spectrographic analysis, (4.2) chemical analysis, (5.1) paramagnetic resonance measurements, and (5.2) the 60-inch cyclotron.
- Chemistry Division, Section C-II, Summary Report For October, November, and December 1952
- This report deals with the (1.1) physical properties of graphite, (1.2) effects of pile irradiation on the properties of graphite, (1.3) effect of irradiation on "ceramic" materials, (1.4) exposure and dosage for radiation damage experiments, (1.5) apparatus for the measurement of the thermal conductivity of solids, (1.6) effects of radiation on ice -- the thermoluminescence of ice, (1.7) investigation of color centers and other optical properties of single crystals. (2.1) radiation chemistry of liquids, (3.1) radiochemical investigation of the spontaneous fission of Cm242, (3.2) radiochemical service, (3.3) on the one-body model of alpha, (4.1) spectrographic analysis, (4.2) chemical analysis, (5.1) the 60-inch cyclotron.
- Chemistry of Gaseous and Condensed Products in Coal Combustion and Conversion Systems
- A recently developed computer program, based on geometric programming, was used to evaluate the chemistry of gaseous and condensed products that arise in conversion of Illinois bituminous coal under both oxidizing and reducing conditions.
- Cladding Failure by Local Plastic Instability
- Cladding failure is one of the major considerations in analysis of fuel-pin behavior during hypothetical accident transients since time, location, and nature of failure govern the early post-failure material motion and reactivity feedback. Out-of-pile thermal transient tests of both irradiated and unirradiated fast-reactor cladding show that local plastic instability, or bulging, often precedes rupture and that the extent of local instability limits the initial rip length. To investigate the details of bulge formation and growth, a perturbation analysis of the equations governing large deformation of a cylindrical shell has been developed, resulting in a set of linear differential equations for the bulge geometry. These equations have been solved along with appropriate constitutive equations and various constraints on the ends of the cladding. Sources for bulge formation that have been considered include initial geometric imperfections and thermal perturbations due to either eccentric fuel pellets or non-symmetric cooling. Of these, only the first is relevant to out-of-pile burst tests. Here it has been found that the most likely imperfection that will grow unstably to failure leads to a bulge around half the circumference with an axial length 1.1 times the deformed diameter. This is in general agreement with burst-test results. For the case of in-reactor fuel pins, it has been found that thermal perturbations can significantly affect local instability, particularly if the deformation process is thermally activated with a high activation energy.
- Class Notes for a PL/I Course
- Presented here are notes for a course in PL/I. They might serve as a guide to those who are developing a course, or as class notes for that course. They might be useful as a textbook independent of any course; as such a textbook, however, they are not self-contained because of the built-in assumption that they will supplement lectures and be accompanied by manuals. Very nearly the full language is taught here, with the emphasis on concepts rather than practical details. Discussion of I/O is avoided until roughly the midpoint of the course. The hoped-for consequence for students is an enhanced perception and understanding of the many concepts and their logical relationships. The dawning of the age of transportability for PL/I programs gives the user a reason, for the first time, to avoid convenient but illegal language.
- A Classification of Lattice Rules Using the Reciprocal Lattice Generator Matrix
- The search for cost-effective lattice rules is a time-consuming and difficult process. After a brief overview of some of the lattice theory relevant to these rules, a new approach to this search is suggested. This -approach is based on a classification of lattice rules using "the upper triangular lattice form" of the reciprocal lattice generator matrix.
- Coal Liquefaction Support Studies
- A development program is being carried out to obtain information applicable to the SYNTHOIL process for converting coal to liquid fuel of low sulfur content. This report presents information on (1) the design of a calorimeter to measure heat of reaction of hydrogen with coal slurries, (2) the design of apparatus and calculations for measuring coefficients of heat transfer from SYNTHOIL process feed and effluent products to process vessel walls, (3) tests on the use of additives to facilitate the removal of solids from oil produced in coal liquefaction processes, and (4) the design and construction of a test unit for evaluating new catalysts for coal liquefaction processes.
- Coal Liquefaction Support Studies
- A development program is being carried out to obtain information applicable to the SYNTHOIL process for converting coal to liquid fuel of low sulfur content. This report presents information on (1) the design of a calorimeter to measure heat of reaction of hydrogen with coal slurries, (2) the design of apparatus and calculations for measuring coefficients of heat transfer from SYNTHOIL process feed and effluent products to process vessel walls, (3) tests on the use of additives to facilitate the removal of solids from oil produced in coal liquefaction processes, and (4) the design and construction of a test unit for evaluating new catalysts for coal liquefaction processes.
- Coal Liquefaction Support Studies
- A development program is being carried out to obtain information applicable to the SYNTHOIL process for converting coal to liquid fuel of low sulfur content. This report presents information on (1) the design of a calorimeter to measure heat of reaction of hydrogen with coal slurries, (2) the design of apparatus and calculations for measuring coefficients of heat transfer from SYNTHOIL process feed and effluent products to process vessel walls, (3) tests on the use of additives to facilitate the removal of solids from oil produced in coal liquefaction processes, and (4) the design and construction of a test unit for evaluating new catalysts for coal liquefaction processes.
- Coal Liquefaction Support Studies
- A development program is being carried out to obtain information applicable to the SYNTHOIL process for converting coal to liquid fuel of low sulfur content. This report presents information on (1) the design of a calorimeter to measure heat of reaction of hydrogen with coal slurries, (2) the design of apparatus and calculations for measuring coefficients of heat transfer from SYNTHOIL process feed and effluent products to process vessel walls, (3) tests on the use of additives to facilitate the removal of solids from oil produced in coal liquefaction processes, and (4) the design and construction of a test unit for evaluating new catalysts for coal liquefaction processes.
- Coal Supply and Air Quality Limitations on Fossil-Fueled Energy Centers
- The coterminous United States is screened on a county-by-county basis to identify areas most likely to provide sites for fossil energy centers (FECs) utilizing local coals and having capacities between 5,000 and 20,000 MWe. Areas eliminated as potential sites include national public lands excluded by legislation, urbanized areas, Air Quality Maintenance Areas for particulates and SO2, and counties where air quality data indicate violations of particulate or SO2 ambient standards. The remaining counties are further screened for suitable coal reserves. The quality of coal required for an FEC to meet emissions and ambient standards is determined for sulfur content and heating value. Based on Bureau of Mines coal reserve data, counties in areas with not enough quality reserves to support an FEC are eliminated. Areas most likely to provide sites for FECs of 5,000, 10,000, and 20,000 MWe, in two different spatial configurations, each with and without flue gas desulfurization are determined and mapped. The possible impacts of regulations for the prevention of significant deterioration are illustrated.
- A Coated Cast Iron Crucible for use with Eutectic Al-Si Alloy in the Temperature Range 595°-650°C
- The feasibility of the coated metal crucible as a container for eutectic Al-Si alloy has been proven by test. Small, enamel-coated cast iron pots has been proven by test. Small, enamel-coated cast iron pots have successfully withstood the chemically aggressive Al-Si alloy and the adverse influence of an oxidizing atmosphere for a period of 3 months at 725°C. A similarly coated castiron crucible containing 450 pounds of eutectic Al-Si alloy was successfully tested for 144 days in a jacketing operation conducted at 595°-650°C. Under the same conditions, the normal service life of clay-bonded graphite and silicon carbide crucibles rarely exceeds 45 days. The coating material is a commercially available enamel capable of withstanding temperatures up to 790°C (1450°F). It is readily applied to the surface of a variety of ferrous metals and alloys; however, best results are obtained with alloys low in chromium and nickel which also have a low thermal expansion coefficient.
- Color Measurements on Marble and Limestone Briquettes Exposed to Outdoor Environment in the Eastern United States
- In a long-term program that began in 1984, limestone and marble briquettes have been exposed to both anthropogenic acid deposition and natural weathering at four field sites in the eastern United States.