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DIMENSIONALLY STABLE ALLOYS. Interim Report

Description: The development of dimensionally stable alloys for high temperature reactor application is discussed. Cold pressing followed by sintering was determined to be the most satisfactory method. Evaluation of alloys by alpha - beta thermal cycling indicated the superiority of U--Mo and U--Nb alloys. A few specimens containing small additions of Mo, Nb, and Si were irradiation tssted in the Materials Testing Reactor. Of these, the Nb alloy (1.6 wt.% Nb) appeared to be most stable. The Mo alloys were somewhat less satisfactory and the alloys containing Si were not stable. (auth)
Date: October 30, 1957
Creator: Eiss, A.L. & Kalish, H.S.
Partner: UNT Libraries Government Documents Department

TBP STRIPPING IN BUBBLE-CAP COLUMN AND CON-COMITANT PRODUCT EVAPORATION

Description: A study was conducted to demonstrate the stripping and evaporation steps in a Purex-type uranium recovery prccess and to ascertain the operating behavior of the equipment under a range of conditions. The factors considered were control, effectiveness, and reliability of equipment and optimum feed pcint. Experimental procedures are described, and recominendations for equipment mcdifications are included. (J.R.D.)
Date: March 18, 1957
Creator: Long, J.T.
Partner: UNT Libraries Government Documents Department

PROGRAMMERS MANUAL FOR THE ORACLE COMPILER

Description: Desirable characteristics for the ORACLE compiler are given and limitations, item format, key words, and crossitem references are discussed. Programming and operating procedure are described. (W.D.M.)
Date: August 23, 1957
Creator: LaVerne, M.E.; Bate, R.R.; Coveyou, R.R.; Sullivan, J.G.; Osborne, B.J.; Downing, A.C. et al.
Partner: UNT Libraries Government Documents Department

PREPARATION OF RADIATION SOURCES FROM FISSION PRODUCTS BY THE CLAY PROCESS

Description: This study was made to determine the feasibility of producing usable radiation sources by the montmorillonite clay process. The clay process was developed at Brookhaven National Laboratory primarily to solve the problem of ultimately disposing of waste fission products. After reviewing the process in detail, it is shown that radiation sources may be prepared with specific activity as high as 4.5 curies of Ce/sup 137/ per gram of clay. Sources of this strength would be entirely suitable for such processing applications as promotion of chemical reactions, preservation of foods, or sterilization of drugs. Furthermore, the operations involved in the clay process are simpler and more straightforward thin those of any other process for making radiation sources from fission products. It is concluded from this study that some clay sources should be prepared to demonstrate the actual process. (auth)
Date: August 1, 1957
Creator: Schoolmeester, J.E. & Martin, J.J.
Partner: UNT Libraries Government Documents Department

SLURRY FLOW METERS AND DENSITY METERS FOR THE HOMOGENEOUS REACTOR

Description: Six types of instruments are being considered for the metering of flow and/or density in high temperature (300 deg C) and pressure (2000 psi) slurry flow systems. Three of these meters yield readings that depend only on the flow rate or the density, one (the Double Rotameter) yields two readings from which both the flow and the density may be determined while another (the venturi) yields a reading that depends on both the flow rate and the density and thus may be either a density-meter or a flowmeter depending on which variable is the unknown. The remaining instrument (the ultrasonic meter) may yield a signal dependent solely on the flowrate or the density depending on the physical setup. This memo briefly describes these instruments, listing their particular advantages, the difficulties that may arise in their use and the state of development of each. (auth)
Date: September 27, 1957
Creator: Wichner, R.P.
Partner: UNT Libraries Government Documents Department

FALLOUT STUDIES AND ASSESSMENT OF RADIOLOGICAL PHENOMENA. Preliminary Report

Description: Data were obtained to evaluate the attenuation of photons, emitted from a fallout field, due to the surface roughness of the terrain. A study was made to determine the effect of the shot tower on the fallout material. Particles for comparison were collected from two detonations of equal scaled height, one tower supported and the other balloon supported. Data on time-dependent phenomena were recorded, as were physical characteristics of the fallout material. The use of small balloons as instrument platforms and a new fallout collector were evaluated for field use. No conclusions or recommendations can be made at this time. (auth)
Date: November 1, 1957
Creator: Egeberg, L.E.
Partner: UNT Libraries Government Documents Department

RECOVERY OF Np$sup 237$ BY THE NEPTEX SOLVENT-EXTRACTION PROCESS

Description: Flowsheets are presented for the solvent extraction recovery of uranium and Np/sup 237/ from special highly irradiated MTR fuel elements and from nonvolatile fluoride residues from the Oak Ridge Gaseous Diffusion Plant. In both cases the material containing the neptunium and uranium is dissolved and digested to inactivate emulsion-forming impurities, the neptunium and uranium are extracted with tributyl phosphate solvent, using aluminum nitrate as the primary salting agent, scrubbed free of fission products and/or ionic contaminants, and finally separated and recovered by selective stripping with nitric acid. (auth)
Date: April 1, 1957
Creator: Flanary, J.R.; Goode, J.H.; Mansfield, R.G. & Wischow, R.P.
Partner: UNT Libraries Government Documents Department

TECHNICAL PROGRESS REPORT. PART I. STUDY PROGRAM ON HIGH-SPEED COMPUTER. PART II. MATHEMATICAL METHODS. PART III. GENERAL RESEARCH. PART IV. ILLIAC USE AND OPERATION--GENERAL LABORATORY INFMATION

Description: Basic circuits used on high-speed eomputers are described and control studies discussed. A prograim has been initiated to study iterative methods for solving systems of linear equations. A new and promising method of minimizing a function of n variables has been found, and a method applicable to evaluating determinants, solving linear algebraic equations, inverting matrices, and determining characteristic equations without round-off error is being tested. The Illiac use and operation for the November period are described. (J.S.R.)
Date: November 1, 1957
Partner: UNT Libraries Government Documents Department

TECHNICAL PROGRESS REPORT. PART I. HIGH-SPEED COMPUTER PROGRAM. PART II. SWITCHING CIRCUIT THEORY. PART III. MATHEMATICAL METHODS. PART IV. GENERAL RESEARCH. PART V. ILLIAC USE AND OPERATION--GENERAL LABORATORY INFORMATION

Description: Transistor circuits and control studies for high-speed computers are described. Combinational and distributive circuits are being investigated in relation to switching circuit theory. Mathematical methods wcre sought for determination of interval size in numerical integration of differential equations. A Monte Carlo Method for studying crystals is described. The use and operation of the Illiac during the month of December are presented. (J.S.R.)
Date: December 1, 1957
Partner: UNT Libraries Government Documents Department

LOW CROSS-SECTION IRON-BASE ALLOYS

Description: Data are presented on the mechanical properties of iron-silicon and iron- aluminum alloys in the range 0 to 14% Si and about 8% aluminum. The effect of third elements on ductility is discussed, and data are prcsented which indicate that it is not possible to obtain a disordered structure in Fe--Si a1loys from 8 to 14% Si. It is concluded that alloys of iron with 6 to 8% aluminum offer a promising base composition for development of low neutron cross section alloys for use in nuclear reactors. (auth)
Date: July 1, 1957
Creator: Lillie, D.W.
Partner: UNT Libraries Government Documents Department

ACCIDENT IN CONTINUOUS-DISSOLVER PILOT PLANT OF FLUORIDE VOLATILITY PROJECT ON MAY 15, 1957

Description: A series of explosions, estimated at five, occurred over a period of ten seconds within the continuous dissolver pilot plant, of the Fluoride Volatility Project on May 15, 1957. The explosive reactions occurred in the dissolver vessels as a result of violent chemical reactions between uranium and an interhalogen mixture. Just what the conditions were which triggered the explosions, have not been definitely established. Nevertheless, based upon the evidence which has been collected, several possible explanations, listed according to probability, are presented. A number of recommendations are included to be followed before operation of the pilot plant is resumed. These recommendations relate to additional laboratory research, equipment design, facility design, and use of a review committee. Safety rules for handling BrF/ sub 3/, BrF/sub 5/, ClF/sub 3/, and Br/sub 2/ are appended. (C.H.)
Date: July 10, 1957
Creator: Strickland, G.; Horn, F.L.; Johnson, R. & Dwyer, O.E.
Partner: UNT Libraries Government Documents Department

PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING OCTOBER 1957

Description: BS>The creep properties of annealed Zircaloy-2, Zircaloy3, and 15% cold- worked Zircaloy-2 at elevated temperatures were determined. The metallurgical bond formed between electropolished U and Zr cladding by hydrostatic pressing is being evaluated. Oxidation data are given for Nb and Nb alloys in dry air at various temperatures. A study of the phase relationships which occur between the delta phases of the U--Zr and U--Mo systems is nearly complete. The solid-solid reactions of some uranium nitrates and carbides at 1800 deg C are given. The creep properties of Ta at 1200 deg F in a helium atmosphere were investigated. (For preceding period see BMI-1226.) (W.L.H.)
Date: November 1, 1957
Creator: Dayton, R.W. & Tipton, C.R. Jr.
Partner: UNT Libraries Government Documents Department

PREPARATION, CLADDING, AND EVALUATION OF TITANIUM-BORON DISPERSIONS

Description: Powder dispersions of titanium--boron and titanium-boron carbide were prepared, clad, and evaluated for use as control materials. Compacts possessing up to 95 per cent of theoretical density were prepared by a hot-pressing technique. The relatively low temperatare of 1500 deg F was used to obtain the desired high density. There was no visible reaction between the boron dispersant and titanium. Excellent metallurgical cladding of the titanium-- boron dispersion with titanium was achieved by the use of both rollbonding and gas pressure-bending techniques. The rolling was performed at 1500 deg F and the pressure bonding was accomplished at 1600 deg F with a helium pressure of 10,000 psi for a time of 6 hr. The pressure-bonding technique produced a specimen with a more uniform boron dispersion and a better high-temperatare-water corrosion resistance than were obtained through roll bonding. Extruded titanium--boron dispersions were joined to hafnium and clad with Zircaloy-2 by a roll-bonding technique to determine in a preliminary way the feasibility of preparing clad composite control rods. Strong, relatively ductile bonds were obtained between all of the components by the rollbonding process and postfabrication heat treatment. (auth)
Date: July 1, 1957
Creator: Paprocki, S.J.; Keller, D.L.; Hodge, E.S.; Cunningham, G.W.; Gedwill, M.A. & Lozier, D.E.
Partner: UNT Libraries Government Documents Department

METALLURGY DIVISION QUARTERLY REPORT FOR JANUARY, FEBRUARY, AND MARCH 1957

Description: Advanced Water Reactor Program. The second fuel loading for the EBWR is planned as ThO/sub 2/--UO/sub 2/. Some properties of ThO/sub 2/-- UO/sub 2/ systems are presented. Fast Power Breeder Reactor Program. The development of casting techniques for EBR-1, Mark III extrusion billet cores are described. The investigation of methods for the remote refabrication of irradiated reactor fuels was undertaken with the objective of designing, constructing, and testing techniques and equipment for the refabrication of EBR-II fuels. Advanced Engineering and Development. From observations amd photographs made during disassembly operations, and from chemical, metallographic, and density measurements, it was possible to reconstruct the probable physical structure of the core after the meltdown of the EBR-1 core. A boiling experiment was performed to give preliminary information as to whether thermal decomposition or volatility would complicate the use of H/sub 3/PO/sub 4/ solution in boiling reactors. Due to the possible use of Mg as a cladding material a few preliminary corrosion tests were made with distilled water. Cylindrical, NaK-filled Zr irradiation capsules, which suddenly broke open during decanning operations following irradiation, were examined in an effort to determine the role of irradiation in these unexpected failures. Production, Treatment, and Properties of Materials. Elastic constants of alpha-U single crystals in three directions were obtained. Recrystallization of heavily cold rolled U sheet was studied. Two ingots of high-purity U was used to study the melting point of U. The eutectic temperature measurements of U--UC alloy are presented. The alpha -- BETA transformation temperatures of highpurity U were studied. Phase diagrams are presented for the U--Ru, U--Ru --Mo, and U--Mo alloys. (For preceding period see ANL-5709.) (W.L.H.)
Date: March 31, 1957
Partner: UNT Libraries Government Documents Department

A COATED CAST IRON CRUCIBLE FOR USE WITH EUTECTIC Al-Si ALLOY IN THE TEMPERATURE RANGE 595-650 C

Description: The feasibility of the coated metal crucible as a container for eutectic Al--Si alloy was proven by test. Small enamel-coated east-iron pets have successfully withstood Al-- Si alloys and an oxidizing atmosphere for a period of 3 months at 725 deg C. A similarly coated east-iron crucible containing 450 pounds of eutectic Al--Si alloy was successfully tested for 144 days in a jacketing operation conducted at 595 deg to 650 deg C. Under the same conditions, the normal service life of clay-bonded graphite and silicon carbide crucibles rarely exceeds 45 days. The coating material for the iron crucible is a commercially available enamel capa ble of withstanding temperatures up to 790 deg C. lt 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. (auth)
Date: November 1, 1957
Creator: Yaggee, F.L.
Partner: UNT Libraries Government Documents Department