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766
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219
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103
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16
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10
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4
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99
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40
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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.
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.
System:
The UNT Digital Library
CALCULATION OF THE REQUIREMENTS FOR OPERATION OF REFRACTORY-METAL COMPONENTS AT HIGH TEMPERATURE IN VACUUM
Equations based on kinetic theory relate the contamination of refractory metals in vacuum to the appropriate variables. Several examples are given for which the allowable system pressures are calculated. The examples illustrate the effect of varying several parameters. The importance of the sticking factor for active gases on hot refractory metals and its effect on the system design are discussed. The data for estimating the sticking factor for O/sub 2/ on Nb are given, along with some estimated values. Experimental data on the composition and rates of outgassing of ultrahigh-vacuum systems and their importance in system design are discussed. Several methods of reducing contamination rates and the relative ease and effectiveness of these methods are presented. It was concluded that tests of 1000 hr or longer will probably require system pressures of between 10/sup -9/ and 10/sup -6/ torr, the particular pressure depending upon the residual gas composition, test duration, allowable contamination level, and the other variables discussed. Since the most important source of contamination in a properly designed ultrahigh-vacuum system is the outgassing process, bakeable systems should be designed to operate with walls as cool as practical, and to have a minimum of surface area and outgassing materials inside. …
Date:
September 18, 1962
Creator:
Clausing, R.E.
System:
The UNT Digital Library
Corrosion Behavior of Reactor Materials in Fluoride Salt Mixtures
Molten fluoride salts, because of their radiation stability and ability to contain both Th and U, offer important advantages as high-temperature fuel solutions for nuclear reactors and as media suitable for nuclear fuel processing. Both applications have stimulated experimental and theoretical studies of the corrosion processes by which molten salt mixtures attack potential reactor materials. Corrosion experiments with fluoride salts which were conducted in support of the Molten-Salt Reactor E xperiment and analytical methods employed to interpret corrosion and masstransfer behavior in this reactor system are discussed. The products of corrosion of metals by fluoride melts are soluble in the molten salt; accordingly passivation is precluded and corrosion depends directly on the thermodynamic driving force of the corrosion reactions. Compatibility of the container metal and molten salt, therefore, demands the selection of salt constituents which are not appreciably reduced by useful structural alloys and the development of container materials whose components are in near thermodynamic equilibrium with the salt medium. Utilizing information gained in corrosion testing of commercial alloys and in fundamental interpretations of the corrosion process, an alloy development program was conducted to provide a high temperature container material that combined corrosion resistance with useful mechanical properties. The program …
Date:
September 19, 1962
Creator:
DeVan, J. H. & Evans, R. B., III
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.
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.
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
System:
The UNT Digital Library
Thermonuclear Division Semiannual Progress Report for Period Ending April 30, 1962
Progress is reported on thermonuclear research. Separate abstracts were prepared for 8 of the 10 sections. Design and engineering service reports and notes are given in the remaining sections. (M.C.G.)
Date:
September 12, 1962
Creator:
unknown
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
System:
The UNT Digital Library
Energy Matrices of the f$sup 5$ Electron Configuration
The complete electrostatic and spin-orbit matrices of the f/sup 5/ electron configuration were calculated and are presented tabularly. (auth)
Date:
September 1, 1962
Creator:
Wybourne, B. G.
System:
The UNT Digital Library
Size effects and interstitial impurities in Nb/sub 3/Zr superconductors. Superconducting solenoids with metal insulation. [Oxygen and carbon]
None
Date:
September 11, 1962
Creator:
Betterton, Jr, J O; Kneip, Jr, G D; Easton, D S & Scarbrough, J O
System:
The UNT Digital Library
GRAPHITE-STAINLESS STEEL COMPATIBILITY STUDIES
S>The compatibility of type 304L stainless steel in intimate contact with graphite is being studied as a function of temperature and contact pressure. This study is an outgrowth of materials compatibility problems in present and advanced gas-cooled reactors, where structural members in direct contact with graphite provide the possibility of both carburization and self-welding. Initial studies were concerned with surface reactions in the absence of gaseous contaminants under a vacuum of 10/sup -6/ mm Hg at 540 to 705 deg C. Stainless steel specimens are pretreated to provide three surface conditions: H/sub 2/- fired, preoxidized, and Cu-plated. Surface contact pressures ranged from 0 to 10,000 psi. Test results are presented which establish the lower temperature limit for significant diffusion between graphite and stainless steel at approximately 60O deg C. Above this temperature, diffusion between untreated or H2-fired stainless steel surfaces was found to effect complete bonding of the two materials at contact pressures as low as 500 psi. Bonding was effectively prevented by the presence of either an oxide film or a Cu plate at temperatures up to 700 deg C. Where bonding occurred, diffusion rates measured for C in stainless steel were comparable with those reported for stainless steel …
Date:
September 25, 1962
Creator:
Fleischer, B.; DeVan, J. H. & Coobs, J. H.
System:
The UNT Digital Library
Military Justice: A Summary of its Legislative and Judicial Development
This report discusses the military justice system and legislation and judicial decisions regarding it.
Date:
September 19, 1969
Creator:
Ujevich, Robert M.
System:
The UNT Digital Library
The Office of Economic Opportunity in 1969: A Chronology of Events
This report provides a chronological listing and discussion of legislative measures related to the activities of the Office of Economic Opportunity in 1969.
Date:
September 11, 1969
Creator:
Zachariasen, Ellen
System:
The UNT Digital Library
Pakistan: Situation Report
This report is the situational report of Pakistan which includes its Political Affairs, Economy, and Foreign Relations.
Date:
September 30, 1968
Creator:
Niksch, Larry A.
System:
The UNT Digital Library
Contingent Election of the President by the House of Representatives and the Vice President by the Senate.
This report describes the Contingent Election of the President by the House of Representatives and the Vice President by the Senate.
Date:
September 16, 1968
Creator:
Tienken, Robert L.
System:
The UNT Digital Library
Powers of the President in the Field of Foreign Policy
This report is categorized in four categories: (I) Power as Commander-in-Chief, (II) Power to appoint and receive Ambassadors,(III) Power by and with the consent of the Senate to make Treaties and (IV) Power as chief Executive.
Date:
September 9, 1969
Creator:
Collier, Ellen C.
System:
The UNT Digital Library
Economic Integration in Latin America: An Annotated Bibliography, 1959-1969
This report provides a bibliography of sources related to economic integration in South America which were published between 1959 and 1969.
Date:
September 29, 1969
Creator:
Billings, Elden E.
System:
The UNT Digital Library
The National Democratic Party (NPD) in Western Germany: Its Background and Present Status
This report discusses the history of radical nationalistic movements in Germany and the creation and influence of the National Democratic Party (NDP) in West Germany, a right-wing nationalistic political party.
Date:
September 29, 1969
Creator:
Fletcher, Patrice A.
System:
The UNT Digital Library
Experimental Breeder Reactor-II (EBR-II) Shield Design
A description of the EBR-II shield and the methods employed in arriving at the final design are presented. The major shield design problems for that reactor are enumerated and discussed. (auth)
Date:
September 1, 1962
Creator:
Grotenhuis, M.; McArthy, A. E. & Rossin, A. D.
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.
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.
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
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.
System:
The UNT Digital Library