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PILOT PLANT SHUTDOWN AND Pu-Al PROCESSING
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.
Object Type:
Report
System:
The UNT Digital Library
Mixing and Evaporation in a Packed Vessel
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 are readily evaporated in spite of the presence of packing in the tank. (auth)
Date:
September 20, 1961
Creator:
Cederberg, C. K. & Buckham, J. A.
Object Type:
Report
System:
The UNT Digital Library
SNAP 2 REACTOR PUMP DEVELOPMENT PROGRAM (RADIAL GAP PERMANENT-MAGNET PUMP)
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 capability of the pump design concept was demonstrated, though further development work is needed to meet the SNAP 2 pump requirements. A flow capacity of 6.8 gpm of NaK at 1000 deg F with a developed head of 3 psi with attained at a magnet rotor speed of 40,000 rpm. The weight of this pump is 3 pounds. Reasonable agreement was obtained between the actual pump characteristics and the design predictions. (auth)
Date:
September 1, 1961
Creator:
Sudar, S.
Object Type:
Report
System:
The UNT Digital Library
Seal-Shell-a Digital Program to Determine Stresses and Deflections in an Axisymmetric Shell of Revolution
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.
Object Type:
Report
System:
The UNT Digital Library
Reactor Development Program Progress Report, August 1961
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
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
CHEMICAL TECHNOLOGY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING MAY 31, 1961
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 granite, solvent extraction technology, mechanisms of separation processes, radiation effects on catalysts, ion exchange technology, chemical engineering research, chemical applications of nuclear explosions, reactor evaluation studies, and assistance programs. (J.R.D.)
Date:
September 21, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Steady State and Transient Thermal and Hydraulic Analysis of SM-2 Termination Report
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 flow transient because the minimum burnout ratio in the hottest element channel of 1.82 is above the minimum design criteria of 1.5. (auth)
Date:
September 1, 1961
Creator:
Segalman, I. & Bradley, P. L.
Object Type:
Report
System:
The UNT Digital Library
ELECTROSTATIC ION-CYCLOTRON PLASMA INSTABILITIES IN A TWO-FLUID HYDRODYNAMIC THEORY
None
Date:
September 1, 1961
Creator:
Wimmel, H.K.
Object Type:
Report
System:
The UNT Digital Library
Data Telemetry Package Powered by Strontium-90 Fueled Generator. Final Report
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, wind direction and barometric pressure are read at the instant of transmission; wind speed is averaged during an eightminute interval and a one-minute interval immediately preceding transmission. A five-watt thermoelectric generator was designed, manufactured and electrically tested for a period of 8.5 months. In May 196l, the generator was fueled with a capsule containing 17,500 curies of Sr/sup 90/. Electrical performance tests were conducted with the integrated system of generator, converter and batteries prior to isotope loading and also after Sr/sup 90/ fueling operations. Weather station compatibility tests were performed in June 1961 and the complete power supply and station housing were packaged for overseas shipment in July 1961. Current residence of the Sr/sup 90/ generator is on Axel Heiberg Island in the Arctic region. (auth)
Date:
September 1, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
SORPTION OF URANIUM ON ZIRCONIUM OXIDE
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 solutions. Conclusions are drawn concerning the relationship between each of these factors and uranium sorption. (auth)
Date:
September 13, 1961
Creator:
Goldstein, G.
Object Type:
Report
System:
The UNT Digital Library
Development of Remote Metallographic Techniques for Irradiated Materials
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 problem. (auth)
Date:
September 1, 1961
Creator:
Carlander, R.
Object Type:
Report
System:
The UNT Digital Library
Interim Report on the Development of an Air Pulser for Pulse Column Application
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 is a considerable improvement over other systems. (auth)
Date:
September 22, 1961
Creator:
Weech, M. E.; P'Pool, R. S. & MacQueen, D. K.
Object Type:
Report
System:
The UNT Digital Library
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
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 required to achieve a given accuracy in monitoring is calculated. Within the precision of the data, there is no evidence for departure from isothermal damaging, hence no positive evidence of radiation annealing at these temperatures and extents of damage. (auth)
Date:
September 1, 1961
Creator:
Primak, W. & Edwards, E.
Object Type:
Report
System:
The UNT Digital Library
GEOMETRICAL CONSIDERATIONS IN THE MEASUREMENT OF THE RATIO L/R IN THE SCATTERING OF POLARIZED NUCLEONS
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 distribution can be represented as a finite power series in the cosine of the angle of emission. A similar representation is used to describe the scattering properties of the analyzer. The integrals over the finite dimensions of the analyzer and detector are evaluated by a standard Newton- Cotes quadrature approximation for multidimensional integration. A discussion of this approximation as well as a listing of the FORTRAN program are included. (auth)
Date:
September 1, 1961
Creator:
Monahan, J.E. & Elwyn, A.J.
Object Type:
Report
System:
The UNT Digital Library
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
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 recipe for pressure ionization was derived which is approximately valid at nondegencrate densities for any ratio of Debye length to ion-sphere radius. Line absorption was evaluated using recent results from pressure-broadening theory and a representation of line series which is computationally as simple as the statistical method. The results show that lines increase the Rosseland mean opacity by a factor which can be nearly ten and which is insensitive to moderate changes in line widths. The code employed generated ionic energy levels internally by isoelectronic interpolation, and is immediately applicable to any- mixture of elements in which no ion has more than 14 bound electrons. The results of the calculations of thermodynamic properties and mean opacities are given in the tables in Appendix A, and the graphs of the monochromatic absorption coefficients are given in Appendix …
Date:
September 1, 1961
Creator:
Stewart, J.C. & Pyatt, K.D. Jr.
Object Type:
Report
System:
The UNT Digital Library
MULTIGROUP CALCULATIONS OF EFFECTIVE NEUTRON FRACTION $beta$eff' PROMPT NEUTRON LIFETIME lp' AND RELATED KINETICS PARAMETERS FOR LARGE, FAST, PLUTONIUM-FUELED REACTORS
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-, 1500-, and 2500-liter cores fueled with plutonium of different isotopic content, which lead to effective delayed-neutron fractions of approximately one-half the values of similar U/sup 235/-U/sup 238/-fueled fast reactors. The energy spectrum and the number of fissions weighted with their importance are recorded in order to reason physically on the obtained parameters. (auth)
Date:
September 1, 1961
Creator:
Sandmeier, H.A.
Object Type:
Report
System:
The UNT Digital Library
Small Power Reactor Projects of the United States Atomic Energy Commission
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
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Anion Exchange in a Large-Scale Agitated Bed
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 anionic complex of thorium nitrate were compared under agitated, pulsed, and fixed bed conditions. (auth)
Date:
September 1, 1961
Creator:
Caracciolo, V. P.
Object Type:
Report
System:
The UNT Digital Library
THEORETICAL STUDY OF OPTICAL PROPERTIES. APPENDIX B: MONOCHROMATIC ABSORPTION COEFFICIENTS FOR HYDROGEN, BERYLLIUM, AND CARBON. Final Report
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
Object Type:
Report
System:
The UNT Digital Library
Quarterly Status Report on LAMPRE Program for Period Ending August 20, 1961
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 continued. Progress is reported in fuel reprocessing. The sodium test facility was operated continuously except for 7 shutdowns required by maintenance, inspection, and equipment modifications. (M.C.G.)
Date:
September 1, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
CERENKOV RADIATION INTENSITY CALCULATIONS FOR Sr$sup 90$ AND Co$sup 60$ IN WATER
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 gamma emitter. The steps necessary to obtain the Compton electron energy spectrum from a gamma emitter are indicated. (auth)
Date:
September 19, 1961
Creator:
Wymer, R.G. & Biggers, R.E.
Object Type:
Report
System:
The UNT Digital Library
Radiological Physics Division Semiannual Report, January-June 1961
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
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Ejection of Large Fragments in High-Energy Nuclear Reactions
Several features of the production of Na/sup 24/ and Mg/sup 28/ fragments produced in the interaction of protons and He ions with Cu, Ag, Au, and U were investigated. Formation cross sections were determined for He ions of different energies between 320 and 880 Mev and for protons of 700 Mev. Thick- target recoil experiments were performed at bombarding energies of 0.7 and 3 Bev for protons, and 880 Mev for He ions. Also given are some recoil measurements of Na/sup 24/ from Al. Analysis of data obtained with target materials heavier than Al showed that for the bombarding energies used, Na/sup 24/ and Mg/sup 28/ are probably produced by the cleavage of the target nucleus into two heavy fragmerts. One of these fragments has a mass approximately equal to the mass Na 4 or Mg/6 and the other contains most of the remaining mass of the target nucleus. However, Na/sup 24/ and Mg/sup 28/ are very probably not slowly evaporated particles nor products of a slow fission process. The experimental information covering fragmentation from photographic emulsion studies and radiochemical studies is discussed. The various mechanisms proposed are considered and a new one suggested. According to this new mechanism Na/sup …
Date:
September 1, 1961
Creator:
Crespo, V. P.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
DETERMINATIONS OF THE KINETICS AND MECHANISMS OF DEBORONIZATION AT 1135 C
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 argon, wet helium, and hydrogen. With the exception of those heat treated in hydrogen, significant boron losses occurred only when a supply of oxygen, either from the sample itself or as a deliberate addition to the heat- treating environment, was available. Correspondingly, the loss mechanism is postulated to be the oxidation of boron to boron sesquioxide and its volatilization from the sample. The loss rate is controlled by the volatilization rate of the oxide which is directly influenced by structure of the compact and sintering environment. Independent of the chemical nature of the matrix, boron losses were incurred during heat treatment in hydrogen. Variations of the water content of the hydrogen from 7 to 460 ppm did not significantly influence …
Date:
September 15, 1961
Creator:
Cherubini, J.H.
Object Type:
Report
System:
The UNT Digital Library