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PILOT PLANT SHUTDOWN AND Pu-Al PROCESSING

Description: The large aqueous pilot plant facilities at ORNL were cleaned and are being put in standby condition. Experience was gained during the year as anion exchange was used to recover more than one kg of plutonium left in the exploded evaporator system. This experience is being applied to a new recovery program just beginning in cell 1 of Building 4507. (auth)
Date: September 25, 1961
Creator: Bresee, J.C.
Partner: UNT Libraries Government Documents Department
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Mixing and Evaporation in a Packed Vessel

Description: In connection with an evaluation of the operability of a 36-inch diameter remote evaporator at the Idaho Chemical Processing Plant that was to be packed with a corrosionresistant neutron-poison packing for criticality control, an investigation in a 30-inch diameter vessel proved that air sparging effectively mixes solutions. The data showed that at similar spar;e rates the presence of the packing caused an increase in the time needed for complete mixing. The investigation showed that solutions … more
Date: September 20, 1961
Creator: Cederberg, C. K. & Buckham, J. A.
Partner: UNT Libraries Government Documents Department
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SNAP 2 REACTOR PUMP DEVELOPMENT PROGRAM (RADIAL GAP PERMANENT-MAGNET PUMP)

Description: A compact electromagnetic pump utilizing a rotating permanent magnet with radial gap was developed for possible application to the SNAP 2 reactor coolant system. The pump was designed for circulation of NaK at 1000 deg F and 11.2 gpm with a developed pressure of 3 psi, operation at 40,000 rpm, minimum weight and size, and high reliability. The performance characteristics of four developmental pump models were measured in a 1000 deg F NaK test loop and compared with design predictions. The capab… more
Date: September 1, 1961
Creator: Sudar, S.
Partner: UNT Libraries Government Documents Department
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Seal-Shell-a Digital Program to Determine Stresses and Deflections in an Axisymmetric Shell of Revolution

Description: SEAL-SRELL, a FORTRAN II program registered as code number M0077 at Bettis Atomic Power Laboratory, is written for the Philco 2000 computer with two tape units. The program is designed to determine loads, deflections, and stresses in a thin shell of revolution under axisymmetric end loads and pressure. (auth)
Date: September 1, 1961
Creator: Friedrich, C.M.
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report, August 1961

Description: Progress is reviewed on the following reactors: EBWR; Borax-V; ZPR-III- ZPR-VI; ZPR-IX; EBR-I; and EBR-II. An outline of fast and slow reactor safety studies in TREAT is presented. Progress is also reported in applied nuclear and reactor physics; development of reactor fuels, materials, and components; heat engineering technology; separation processes; and advanced reactor concepts. (T.F.H.)
Date: September 15, 1961
Partner: UNT Libraries Government Documents Department
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CHEMICAL TECHNOLOGY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING MAY 31, 1961

Description: Activities in research programs are summarized in the areas of power reactor fuel processing, fluoride volatility processing, molten salt reactor fuel processing, homogeneous reactor fuel processing, waste treatment and disposal pilot plant decontamination, GCR coolant purification studies, equipment decontamination, HRP thoria blanket development, fuel cycle development, transuranium element studies, production of U/sup 232/, uranium processing, fission product recovery, thorium recovery from … more
Date: September 21, 1961
Partner: UNT Libraries Government Documents Department
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Steady State and Transient Thermal and Hydraulic Analysis of SM-2 Termination Report

Description: Thermal characteristics of the SM-2 core were analyzed at steady state and loss of flow conditions. For steady state operation, the steady state code STDY-3 was used. For transients during-a loss of flow acident, ART-02, a onedimensional code, was used. This analysis indicated the SM-2 core is safe from burnout under steady state operation at design power level (28 Mw(t)) because no nucleate boiling exists, and the minimum burnout ratio is above 2.0. The core is safe from burnout under loss of … more
Date: September 1, 1961
Creator: Segalman, I. & Bradley, P. L.
Partner: UNT Libraries Government Documents Department
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Data Telemetry Package Powered by Strontium-90 Fueled Generator. Final Report

Description: An automatic, nuclear powered, meteorological data transmitting radio station was designed and fabricated for unattended service at a remote Arctic location. The system automatically measures air temperature, barometric pressure, wind direction, and two wind speed averages- Once every three hours it transmits this data in binary digital form, on two frequencies, to a manned receiving station (also designed as a part of this contract) where it is recorded on a two-channel recorder. Temperature, … more
Date: September 1, 1961
Partner: UNT Libraries Government Documents Department
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SORPTION OF URANIUM ON ZIRCONIUM OXIDE

Description: The sorption of the ions of uranium, copper, and nickel on hydrous zirconium oxide was investigated at temperatures from 25 to 250 deg C. The experiments were performed by equilibrating 5 ml of the test solution with 0.5 g of zirconium oxide in a titanium autoclave, which was heated by means of a rocking furnace. The sorption of uranium was affected by characteristics of the zirconium oxide, temperatare of equilibration, and concentrations of uranium and of free acid in the uranyl sulfate solut… more
Date: September 13, 1961
Creator: Goldstein, G.
Partner: UNT Libraries Government Documents Department
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Development of Remote Metallographic Techniques for Irradiated Materials

Description: A remote metallographic facility is in operation at Argonne National Laboratory. Techniques relative to better contamination control and equipment operation were developed. The techniques used for microscopic examination of irradiated materials were standardized with variations only in the final polishing steps, and detailed procedures are given for several alloys. The procedures used for macroscopy vary from sample to sample, and new procedures are developed as required to suit each particular… more
Date: September 1, 1961
Creator: Carlander, R.
Partner: UNT Libraries Government Documents Department
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Interim Report on the Development of an Air Pulser for Pulse Column Application

Description: The Idaho Chemical Processing Plant for several years has been studying various pulsing systems, used in extraction columns for processing irradiated nucIear fuel elements, in an effort to eliminate the mechanical difficuittes in present pulsing systems. An air puising system has been demonstrated, and a discussion is given of experimental work, pulser design, and plant operational experience with this system. It is concluded, from work completed thus far that air puising of extraction columns … more
Date: September 22, 1961
Creator: Weech, M. E.; P'Pool, R. S. & MacQueen, D. K.
Partner: UNT Libraries Government Documents Department
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RADIATION DAMAGE RATES IN NUCLEAR REACTORS. I. THE ELECTRICAL RESISTANCE OF GRAPHITE OVER THE TEMPERATURE RANGE 8-90 C: INITIAL DAMAGE AND ITS TEMPERATURE COEFFICIENT

Description: The behavior of 0.125-in. spectroscopic graphite rods is shown to be variable beyond the variation of measurement. Statistical measures are given for the variability before and with irradiation. The linear regression of the reciprocal per cent change in resistance against the reciprocal exposure was determined from 25 to 90% change of electrical resistance. The linear regression of the above regression coefficients was determined for the range from 8 to 90 deg C. The number of specimens require… more
Date: September 1, 1961
Creator: Primak, W. & Edwards, E.
Partner: UNT Libraries Government Documents Department
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GEOMETRICAL CONSIDERATIONS IN THE MEASUREMENT OF THE RATIO L/R IN THE SCATTERING OF POLARIZED NUCLEONS

Description: A FORTRAN II program is described which is used to evaluate the effect of a spatially extended analyzer and detector on the measurement of the left- right asymmetry in the scattering of polarized particles. The initial scatterer is assumed to be a point source and the analyzer, second scatterer, and detector are treated as planes whose dimensions are adjustable as input data in the program. The calculation allows for any glven angular distribution of particle flux from the source if this distri… more
Date: September 1, 1961
Creator: Monahan, J.E. & Elwyn, A.J.
Partner: UNT Libraries Government Documents Department
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THEORETICAL STUDY OF OPTICAL PROPERTIES. PHOTON ABSORPTION COEFFICIENTS, OPACITIES, AND EQUATIONS OF STATE OF LIGHT ELEMENTS INCLUDING THE EFFECT OF LINES. Final Report. APPENDIX A: THERMODYNAMIC PROPERTIES AND MEAN OPACITIES

Description: Photon absorption coefficients and mean opacities were calculated for hydrogen, beryllium, carbon, nitrogen, aluminum, and silicon over a temperature range froni l.5 to 34 ev and a density range from about l0/sup -1/g/cm/sup 3/ downward. Contributions to the absorption coefficient from free-free (inverse- bremsstrahlung), bound-free (photoelectric), and bound-bound (line-absorption) processes are included, as is Compton scattering. Certain thermodynamic properties are also given. An improved re… more
Date: September 1, 1961
Creator: Stewart, J.C. & Pyatt, K.D. Jr.
Partner: UNT Libraries Government Documents Department
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MULTIGROUP CALCULATIONS OF EFFECTIVE NEUTRON FRACTION $beta$eff' PROMPT NEUTRON LIFETIME lp' AND RELATED KINETICS PARAMETERS FOR LARGE, FAST, PLUTONIUM-FUELED REACTORS

Description: Large, plutonium-fueled, fast reactors will have a different kinetic behavior than fast reactors fueled with U/sup 235/, due to the much smaller delayed-neutron fraction emitted in the fissioning of plutonium. The fissioning of Pu/sup 240/, Pu/sup 241/, Pu/sup 242/, and especially U/sup 238/, which emit mor e delayed neutrons per fission than Pu/sup 239/, introduces a considerable increase in BETA /sub eff/ over that for a hypothetical pure Pu/sup 239/ reactor. The cases considered are 800-, 15… more
Date: September 1, 1961
Creator: Sandmeier, H.A.
Partner: UNT Libraries Government Documents Department
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Small Power Reactor Projects of the United States Atomic Energy Commission

Description: Information on small power reactor projects of the USAEC is summarized. General information concerning the projects as a whole is given. Specific projects discussed include: the Elk River Power Reactor, the Piqua Nuclear Power Facility, the BONUS Power Reactor, the Pathfinder Power Reactor, the small-size pressurized water power reactor, and the experimental low-power process heat reactor. (M.C.G.)
Date: September 28, 1961
Partner: UNT Libraries Government Documents Department
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Anion Exchange in a Large-Scale Agitated Bed

Description: An agitated ion exchange column was adapted for use in a large radiochemical separations plant. Tests with nonradioactive solutions showed that ion exchange resin could be charged to and discharged from the column through typical plant piping and without the use of mechanical valves. With the agitator turning, the bed passed solutions containing 400 ppm of finely divided silica whereas a fixed bed became plugged. The pressure drop through the column and the absorption characteristics of an anio… more
Date: September 1, 1961
Creator: Caracciolo, V. P.
Partner: UNT Libraries Government Documents Department
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THEORETICAL STUDY OF OPTICAL PROPERTIES. APPENDIX B: MONOCHROMATIC ABSORPTION COEFFICIENTS FOR HYDROGEN, BERYLLIUM, AND CARBON. Final Report

Description: No abstract.<><DSN>16:004155<ABS>No abstract.<><DSN>16:004156<ABS>Nitrosylium hexafluoroniolybdate(V) and nitrosylium hexafluorouranate(V) were prepared and characterized. These compounds were prepared by the reaction of nitric oxide with the respective hexafluoride. Nitric oxide did not react with tungsten hexafliioride. Nitrous oxide was found to be unreactive toward molybdenum, tungsten, and uranium hexafluorides. (auth)
Date: September 1, 1961
Creator: Stewart, J C & Pyatt, Jr, K D
Partner: UNT Libraries Government Documents Department
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Quarterly Status Report on LAMPRE Program for Period Ending August 20, 1961

Description: BS>All basic experiments planned for the LAMPRE I startup program were completed. The tests included operation at 100 and 200 kw utilizing both normal and half coolant flow, and full flow operation at 400 kw. At each power level, transfer function measurements were made, and a continuous run of approximately 60 hr duration was carried out to determine the characteristics of the reactivity loss first observed at 50 kw. Various power demand tests were made. Fuel and container development was cont… more
Date: September 1, 1961
Partner: UNT Libraries Government Documents Department
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CERENKOV RADIATION INTENSITY CALCULATIONS FOR Sr$sup 90$ AND Co$sup 60$ IN WATER

Description: A method for calculating Cherenkov radiation intensity from an initial electron energy distribution is presented. The Cherenkov radiation intensity from 1 curie of Sr/sup 90/ in secular equilibrium with Y/sup 90/ in water was calculated from the beta energy spectrum to illustrate the use of the method for a pure beta emitter. The Cherenkov radiation intensity from 1 curie of Co/sup 60/ in water was calculated from the Compton electron energy spectrum to illustrate the use of the method for a ga… more
Date: September 19, 1961
Creator: Wymer, R.G. & Biggers, R.E.
Partner: UNT Libraries Government Documents Department
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Radiological Physics Division Semiannual Report, January-June 1961

Description: Twenty papers are presented on various projects pursued in the Radiologmcal Physics Division. The topmcs of the papers include radioactivities of bone and air, cesium137 content in human subjects, liquid scintillators, fluid flow, and air and soil temperature cycles. Separate abstracts were prepared for 16 of the papers. (D.L.C.)
Date: September 1, 1961
Partner: UNT Libraries Government Documents Department
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DETERMINATIONS OF THE KINETICS AND MECHANISMS OF DEBORONIZATION AT 1135 C

Description: The mechanisms and kinetics of the loss of boron during heating at 1135 deg C under various dynamic environments were determined from powder compacts of 5 wt% elemental boron dispersed in matrices of Fe, Cr, Ni, Si, Fe/sub 2/O/sub 3/, Cr/sub 2/O/sub 3/, NiO, and SiO/sub 2/, compacts of austenitic stainless steel alloy powder containing 0.25 wt% boron, and wrought specimens of 0.13 wt% boron-- stainless steel alloy. The compacts containing 5 wt% boron were heat treated in vacuum, highpurity argo… more
Date: September 15, 1961
Creator: Cherubini, J.H.
Partner: UNT Libraries Government Documents Department
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Decontamination of Cells 6 and 7, Building 3019, Following Plutonium- Release Incident

Description: As a result of the evaporation explosion in the Radiochemical Processing Pilot Plant on Nov. 20, 1959, two cells were contaminated with plutonium to a transferable level of 10/sup 8/ d/m/100 sq cm. The area involved measures 40 by 20 by 27 ft high with a total surface area, including equipment, of 10,000 sq ft. The cells were decontaminated by a factor of 1000 in five months by removing loose equipment, debris, and shielding blocks and flushing with 430,600 liters of various decontaminating rea… more
Date: September 11, 1961
Creator: Parrott, J.R.
Partner: UNT Libraries Government Documents Department
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