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Effect of Heat Flux on the Corrosion of Aluminum by Water. Part Iii. Final Report on Tests Relative to the High-Flux Isotope Reactor
The effect of very high heat fluxes on the corrosion of 1100 and 6061 aluminum alloys by water was investigated. The test conditions generally simulated those expected to exist during operation of the High-Flux lsotope Reactor. At heat fluxes between 1 and 2 x l0/sup 6/ Btu/hr-ft/sup 2/ and with coolant temperatures and velocities in the ranges of 13l to 250 deg F and 3l to 51 fps, respectively, a layer of boehmite ( alpha Al/sub 2/O/sub 3/- H/sub 2/0), which has low thermal conductivity, formed on the water-cooled aluminum surfaces during test. When only relatively thin films formed, the boehmite adhered tightly to the aluminum, but in those cases where relatively thick films formed, some boehmite spontaneously spalled from the surface. The rate at which the boehmite formed on the surface (and consequently the rate at which the aluminum temperature increased) was a function of the temperature at the specimen-water interface and the pH of the coolant. The lower the temperature and the lower the pH (in the range of 5.0 to 6.5 with HNO/sub 3/), the lower the rate of corrosion- product formation. Within the ranges investigated, pressure and flow rate were without effect, and the same results …
Date:
December 20, 1961
Creator:
Griess, J. C.; Savage, H. C.; Rainwater, J. G.; Mauney, T. H. & English, J. L.
Object Type:
Report
System:
The UNT Digital Library
Biological Effects of Blast. Technical Progress Report
The current state of knowledge relevant to biological blast effects was summarized in a selective manner. Initially, five problems of concern to those who would relate the environmental variations produced by nuclear weapons with biological response and hazard assessment were pointed out. Primary, secondary, tertiary, and miscellaneous blast effects were defined and selected interspecies experimental data of a physical and pathophysiological nature useful in estimating human response were presented. Tentative biological criteria defining safe levels of exposure were set forth as were survival curves for different conditions of exposure in Hiroshima. These were discussed along with the comparative variations in range of the free-field effects as they vary with explosive yield. The fundamental requirement for surviving seconds, minutes, and hours to abet survival for days, weeks, months, and years was emphasized along with the necessity for planning protective measures against all hazardous weapons effects as one attractive alternative for minimizing casualties and maximizing survival in the event of a nuclear war. (auth)
Date:
December 1, 1961
Creator:
White, C. S.
Object Type:
Report
System:
The UNT Digital Library
Adsorption of Krypton and Xenon by Various Materials
The adsorptive capacities of various inorganic adsorbents and activated charcoals for krypton and xenon were determined. Columbia-G activated charcoal had the highest capacity for both krypton and xenon at pressures from 0.01 to 125 mm Hg and temperaturens from 2 to 85 deg C. If a value of 1 is assigned to the capacity of this charcoal at 28 deg C for krypton, other charcoals range from 0.63 to 0.84, molecular sieves (except 4A) from 0.11 to 0.20, and some silica genls from 0.05 to 0.07. Various othenr adsorbennts, including one variety of silica gel and molecular sieve 4A, range from 0.005 to 0.032. Molecular sienve 5A and Columbia-G charcoal adsorbed 11.5 times more xenon than krypton. Adsorption of 7.5% water by either of these adsorbents lowerend their capacity for krypton 25 to 30%, while saturating the sieve material ( approximates 15% H2O) lowered the krypton capacity 80%. (auth)
Date:
December 1, 1961
Creator:
Lloyd, M. H. & McNees, R. A.
Object Type:
Report
System:
The UNT Digital Library
Chemical Technology Division, Unit Operations Section Monthly Progress Report, May 1961
The experimental results on the oxidation of H from a He stream with CuO pellets were very close to the predicted behavior based on the mathematical model. Experimental measurements of uranyl sulfate loading rates on chloride equilibrated resin showed little variation with solution concentrations. A tentative flowsbeet was proposed for cost analysis of processing a Pebble Bed Reactor. A U-Zr plate was dissolved in nitrate-free Zirflex solution. An authentic TRIGA prototype was processed in engineering-scale equipment. Three 4- stage leacher model dissolution runs were made, two of which used 8 M HNO/sub 3/ and one used 4 M HNO/sub 3/. Flooding rates and holdup data were obtained for sieve plate pulse columns under 5% TBP - l.8 Mi Al(NO/sub 3/)/sub 3/ flowsheet conditions. A Purex waste calcination run (R-37) was made using sodium anid imagnesium to reduce sulfate volatility. (auth)
Date:
December 26, 1961
Creator:
Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Object Type:
Report
System:
The UNT Digital Library
SOLID STATE DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING AUGUST 31, 1961
Progress in solid state physics is reported on the following topics: theory, metals and alloys, nonmetals, reactor materials, and special projects. Twenty-one separate abstracts were prepared. (M.C.G.)
Date:
December 29, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
SEPARATION OF TRANSPLUTONIUMS FROM LANTHANIDES BY TERTIARY AMINE EXTRACTION
None
Date:
December 20, 1961
Creator:
Baybarz, R.D. & Weaver, B.
Object Type:
Report
System:
The UNT Digital Library
Noise Considerations in Nuclear Pulse Amplifiers
The effects of certain pulse-shaping networks on the signal-to-noise ratio of a nuclear pulse amplifier were considered. The shaping networks discussed are: equal RC-integrating and RC-differentiating time constant, single- delay-line clipper and RC integrator, and doubledelay-line clipper and RC integrator. The effects of these networks on the signal, when high count rates and overload pulses are present, were also considered. Equations and curves were developed for the energy resolution (signal-tonoise ratio) and resolving time (related to the ability to operate at high counting rates) of the networks. Experimental results are shown for the energy resolution of the types of pulse- shaping networks considered. (auth)
Date:
December 20, 1961
Creator:
Landis, D. A.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
Heat Transfer With Laminar Flow in Concentric Annuli With Constant and Arbitrary Variable Axial Wall Temperature
An analysis has been performed to determine the heat transfer characteristics for laminar forced-convection flow in a concentric annulus with prescribed surface temperatures. Three distinct problems were considered: (a) wall temperature prescribed at both the inside and outside wall; (b) inside wall temperature prescribed and the outside wall insulated; and (c) inside wall insulated and outside wall temperature prescribed. The solution for temperature distribution was similar to that obtained by Graetz for laminar heat convection in a pipe with uniform wall temperature. Expressions are presented for heat flux, mixing cup temperature, and Nusselt number as a function of downstream position. Eigenvalues and eigenfunctions were computed for values of the ratio of the inside to the outside radii for the boundary conditions. Mixing cup temperatures, local and fully developed Nusselt numbers, and thermal entry lengths are presented graphically. The solution of Problem (a) was extended to the situation in which the temperatures of the inside and outside walls of the annulus are not equal. By utilizing the method of superposition and the solutions already obtained for Problem (a), the temperature distributions were determined. By way of illustration, heat fluxes were calculated for several values of the temperature ratio (T/sub wi/-T/sub 0/)/(T …
Date:
December 1, 1961
Creator:
Viskanta, R.
Object Type:
Report
System:
The UNT Digital Library
DEVELOPMENT OF RING-JOINT FLANGES FOR USE IN THE HRE-2
Ring-joint flanges were studied in thermal-cycle tests as part of the development work associated with Homogeneous Reactor Experiment No. 2 (HRE-2). The purpose of this study was to provide criteria for design, installation, and operation of joints that would remain leaktight under reactor operating temperatures and pressures. Joints ranging from 1/2 in., l500 lb to 4 in., 2500 lb and with various initial bolt loadings were cycled between room temperature and 636 deg F. It was demonstrated that when joints were made up to HRE-2 standards and specifications, leak rates of less than 0.25 x 10/sup -3/ g of water per day per inch of gasket pitch diameter could be routinely- attained. Undamaged gaskets could be reinstalled or new gaskets used with equal probability of achieving acceptable leak rates. The system installed in HRE-2 was provided with a high-pressure buffer system to ensure that the small amount of leakage to the cell would be nonradioactive. (auth)
Date:
December 21, 1961
Creator:
Robinson, J. N.; Lundin, M. I. & Spiewak, I.
Object Type:
Report
System:
The UNT Digital Library
A Summary of Industrial Accidents in USAEC Facilities
The summary includes descriptions of serious accidents for l959 and 1960, AEC industrial injury frequency rates, criticality accidents, radiation exposures, accidents involving radioactive materials in AEC activities during 1959 and 1960, and accidents involving fatalities in AEC activities during l959 and 1960. (B.O.G.)
Date:
December 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
REMOTELY CONTROLLED SHEARING OF PIPE AND STRUCTURAL MEMBERS
A shearing tool was developed for remotely controlled severing of pipes or structural members. The shear is rotated about its axis in a wrist motion by the pumped hydraulic fluid that also powers the shear blade. It can be used in a stationary mounting or suspended from a crane. A C-shaped support for the shear was designed to pass through a small top opening of a shielded cell. The controls for manipulating the shear pass through or along the Cframe. The shear jaw opens to 5 in. in height and 7 in. in width, and the total weight of the tool is only 575 lb. It was used to cut metal sections 4 3/4 in. thick and 4-in. sched.-40 stainless steel pipe. (auth)
Date:
December 28, 1961
Creator:
Abbatiello, A. A.
Object Type:
Report
System:
The UNT Digital Library
WEATHER MODIFICATION
It is suggested that applying heat directly to a rain cloud, or to a ndoist air mass with rain potential, may alter the natural precipitation in a given geographical region. The immediate effect of the heat is to increase the buoyancy of the cloud or air parcel. The result, which depends on a number of interrelated factors may be either to cause precipitation where it would not naturally occur, or to suppress precipitation where it would naturally occur. Several possible applications are suggested. Since the heat supplied is supplemented by the latent heat resulting from condensation in the moist air mass, the results may more than justify the cost. However, substantial amounts of heat are involved. The heat can be supplied from fossil fuels, nuclear reactions, or a combination of both; but the logistics favor the use of large nuclear reactors wherever safety criteria can be met. Not only the efficiency and economics of the process, but also its feasibility, can be finally decided only on the basis of information that is not now available. (auth)
Date:
December 1, 1961
Creator:
Rodin, M.B. & Hess, D.C.
Object Type:
Report
System:
The UNT Digital Library
TITANIUM PUMP LOOP FOR AQUEOUS SOLUTIONS AT HIGH TEMPERATURES
A titanium pump loop, designed to circulate aqueous solutions at temperatures and pressures up to 370 deg C and 3000 psia, was constructed. It is to be used to study the chemical stability of uranyl sulfate fuel solutions of interest to the Fluid Fuels Reactor Program. The total loop voluime was minimized so that about 2 liters uf solution was sufficient for loop operation. The equipment includes a sampling system to remove solution samples from the loop while operating at elevated temperature and pressure; a hydroclone to separate and remove any solids and/or heavyphase material formed; and provisions for installation of corrosion test specimens in the main loop stream. All equipment performed satisfactorily at design conditions in tests with water. (auth)
Date:
December 13, 1961
Creator:
Baker, J.M. & Bolt, S.E.
Object Type:
Report
System:
The UNT Digital Library
ELECTROLYTIC DISSOLUTION OF NUCLEAR FUELS. PART I. ZIRCONIUM IN HCl- METHANOL
The electrolytic dissolution of zirconium in HCl-methanol was studied as a function of potential, solution composition, and temperature. The dissolution is characterized by two regions. At high potentials the zirconium is electropolished and complete dissolution is achieved. At low potentials the current is an exponential function of the potential (Tafel behavior). In this region a small amount of finely divided alpha -zirconium which is insoluble in HCl-methanol separates from the bulk metal. The energy of activation for the corrosion reaction (0.0 volt) is 16.5 kcal/mole; in the electropolishing region (1.0 volt) the activation energy is 7.7 kcal/mole. A broad solvent capability for metallic reactor fuels is offered by the HCl-methanol medium since, in addition to zirconium, stainless steel is also dissolved electrolytically while uranium and aluminum dissolve chemically. Other process implications are discussed. (auth)
Date:
December 29, 1961
Creator:
Aylward, J. R.; Whitener, E. M. & Hahn, H. T.
Object Type:
Report
System:
The UNT Digital Library
GETTING MULTICHANNEL ANALYZER DATA IN AND OUT OF THE IBM-7090 FOR PROCESSING
The present method used for handling multichannelanalyzer data at the ORNL 86-Inch Cyclotron is stated. FORTRAN subroutines for reading the analyzer data into the IBM-7090 computer and for printing out the processed data and punching processed data on cards are presented. (auth)
Date:
December 12, 1961
Creator:
Goodman, C. D.
Object Type:
Report
System:
The UNT Digital Library
Phase Transformations in Alumina. Technical Report, May to December 1961
e transformation studies showed that synthetic aluminas produced in the laboratory were not transformed to alpha alumina at 400 to 700' deg n the presence of nitric acid and water vapor. Amorphous aluminn produced in the pilot plant was transformed to alpha alumina. This indicated that the amorphous alumina produced in the pilot plant is structurally predisposed to form alpha alumina. Most additives did not appear to have any special effects. Lithium formed zeta alumina, LiAl/sub 5/O/sub 8/. Phosphate formed an unidentified phase. Zinc formed zinc aluminate. Sulfate favored higher water and lower nitrate contents than any of the other additives and formed natroalunite in one sample. The synthetic aluminas were heated in the micro reactor at pressures of 150 to 1300 psi. Most of the synthetic aluminas containing sodium formed alpha alumina while those without sodium did not, which agreed with the pilot plant results. Additives which allowed alpha alumina to form were calcium, iron, and lithium. Potassium, silicate, sulfate and zinc allowed alpha alumina to form when sodium was also present. Phosphate, boric acid, and magnesium seemed to prevent the formation of alpha alumina. Fission products, at 10 times the expected amount, also appeared to prevent formation of …
Date:
December 1, 1961
Creator:
Eding, H J; Huggins, M L & Brown, A G
Object Type:
Report
System:
The UNT Digital Library
Quarterly Status Report on Ultra High Temperature Reactor Experiment (UHTREX) for Period Ending November 20, 1961
The detailed design of the reactor proper was essentially completed and preparations were made for procurement of the carbon components and the pressure vessel. Design of the UHTREX facility has progressed to Titie lI. Design information is included on copper oxide beds and molecular sieves for gas cleanup. In other work, irradiation of capsules containing UHTREX fuel elements is reported along with fuel recycle research. (J.R.D.) 9578(Faye unscannable abstract)
Date:
December 1, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
COOLING OF THE HFIR BERYLLIUM REFLECTOR FOLLOWING A REACTOR SCRAM OR AN ELECTRICAL POWER OUTAGE
Thermal stresses in the HFIR beryllium reflector were computed for the unlikely case where the reactor is scrammed with a simultaneous loss of coolant flow and for the case following an electrical power outage where the reactor power level and the coolant flow rate are reduced simultaneously. For the case where the reactor is scrammed with a sudden loss of the coolant flow, the resulting maximum tensile thermal stress following the scram is 22,500 psi. In case of an electrical power outage, the maximum tensile thermal stress following a reduction of the fission power level from 100 Mw to 10 Mw with the lowering of the coolant flow rate to 10% of the normal value is 12,800 psi. (auth)
Date:
December 12, 1961
Creator:
McLain, H. A.
Object Type:
Report
System:
The UNT Digital Library
EXPERIMENTAL ATTEMPTS TO STABILIZE A CUBIC FORM OF BeO
Binary mixtures of BeO with the oxides Al/sub 2/O/sub 3/, CaO, Li/sub 2/ O, MgO, Sc/sub 2/O/sub 3/, TiO/sub 2/, Y/sub 2/O/sub 3/, and ZrO/sub 2/ were fired to temperatures in excess of 2050 deg C in an attempt to produce a stabilized cubic crystalline modification of BeO. No evidence was observed in microscopic and x-ray diffraction analyses of the cooled specimens that a cubic form of BeO had formed in the experiment. (auth)
Date:
December 22, 1961
Creator:
Thoma, R.E.; Friedman, H.A. & McVay, T.N.
Object Type:
Report
System:
The UNT Digital Library
POSTIRRADIATION EXAMINATION OF 17-4 PH STAINLESS STEEL CONTROL ROD DRIVE RACK FROM SM-1 REACTOR
A portion of the control rod drive system in the SM-1 Reactor, fabricated from l7-4 PH stainless steel, was examined at the Oak Ridge National Laboratory (ORNL) hot cells after successful operation in a pressurized-water environment for approximately three years. Examination included visual inspection, magnetic-particle tests, fluorescent penetrant tests, and metallography. No evidence of stress-corrosion cracking or other damage was noted. (auth)
Date:
December 1, 1961
Creator:
Klindt, K.K.; Richt, A.E. & Thurber, W.C.
Object Type:
Report
System:
The UNT Digital Library
Irradiation of Metal-Fiber-Reinforced Thoria-Urania. Final Report- Metallurgy Program 6.2.4
Randomly oriented fibers of either molybdenum or niobium were incorporated into hot-pressed pellets of 10, 30, and 50 wt% UO/sub 2/ in ThO/sub 2/ to improve thermal conductivity and thermal shock resistance. Pellets, 9.5 mm in diameter and 9.5 mm in length, were irradiated in NaK capsules, both bare and jacketed with Zircaloy-2, with the annulus between pellet and jacket filled with lead or helium. They were irradiated to burnups ranging up to 34 500 Mwd/T (1 0 x 10/sup 21/ fiss/cc) at central temperatures of the order of 3000 deg C. Integral kd theta values ranged from 34 to 129 w/cm. Fracture and metallographic sections of the irradiated specimens confirmed out-of-pile measurements that the molybdenum fibers increased the effective thermal conductivlty of the mixed oxides. It was possible to give the fibered pellets higher heat ratings than unfibered pellets before comparable thermal effects occurred. The fibers tended to reduce central void formation, retard recrystallization, and maintain the integrlty of the pellet. In some helium- bonded specimens, the molybdenum fibers coalesced into a central sphere after melting during irradiation. The coalescence did not occur in lead-bonded specimens. The niobium fibers were found to react with the oxide. Fission gas release …
Date:
December 1, 1961
Creator:
Neimark, L. A.; Kittel, J. H. & Hoenig, C. L.
Object Type:
Report
System:
The UNT Digital Library
MARITIME GAS-COOLED REACTOR PROGRAM. A REVIEW OF THE MARITIME GAS-COOLED REACTOR PROGRAM
Presented at the Eleventh Professional Divisions Conference of the San Francisco Section of the American Society of Mechanical Engineers, Noveraber l6, l96l. The MGCR program and its objectives are discussed. The basic MGCR plant is described. The design of the Experimental Beryllium Oxide Reactor is also described. (M.C.G.)
Date:
December 22, 1961
Creator:
Trickett, K.A.
Object Type:
Report
System:
The UNT Digital Library
ON THE REALITY OF THE EIGEN-VALUES FOR A ONE-GROUP N-REGION DIFFUSION PROBLEM
A sufficient condition is presented for the reality of the eigen-values for a fairly general one-group, multiregion two-dimensional diffusion problem. The condition is also sufficient to insure the orthogonality of eigen-functions corresponding to distinct eigen-values. (D.L.C.)
Date:
December 1, 1961
Creator:
Hildebrandt, T.W.
Object Type:
Report
System:
The UNT Digital Library
An Integral Design Technique for Wideband Multistage Transistor Amplifiers
A philosophy for designing wideband multistage transistor amplifiers is presented. The amplifier was visualized as an integral unit, the interstage networks constituting the elements of the amplifier unit. By designing the amplifier as a unit and adjusting the over-all response (gain and bandwidth) with the interstage time constants, an increase in gain-bandwidth product was realized over the iteratively designed amplifiers. The resulting increase in gainbandwidth product resulted from absence of the bandwidth shrinkage factor for multistage amplifiers. Formulas were derived for both a two- and three- transistor integrally designed wideband amplifier, in which shunt peaking networks were used for coupling. Experimental amplifiers were con structcd following these formulas, and the observed performance agreed quite well with the calculations. (auth)
Date:
December 14, 1961
Creator:
Scott, L.
Object Type:
Report
System:
The UNT Digital Library