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Advanced Fuel Cell Development Progress Report: April-June 1979

Description: Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes efforts directed toward understanding and improving the components of moltencarbonate-electrolyte fuel cells operated at temperatures near 925 K.
Date: November 1979
Creator: Pierce, R. D.; Finn, P. A.; Kinoshita, K.; Kucera, G. H.; Poeppel, R. B.; Singh, R. N. et al.
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Advanced Fuel Cell Development: Progress Report for July-September 1978

Description: Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes activities focuses on the development of electrolyte structures that have good electrolyte retention and mechanical properties as well as long term stability, and on developing methods of synthesis amenable to mass production.
Date: May 1979
Creator: Ackerman, J. P.; Pierce, Robert Dean; Nelson, P. A.; Arons, R. M.; Kinoshita, K.; Sim, J. W. et al.
open access

Advanced Fuel Cell Development Progress Report: January-March 1979

Description: Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes efforts directed toward understanding and improving the components of molten-carbonate-electrolyte fuel cells operated at temperatures near 925 K. The primary focus of this work has been the development of electrolyte structures that have good electrolyte retention and mechanical properties as well as long-term stability, and on developing methods of synthesis amendabl… more
Date: September 1979
Creator: Pierce, R. D.; Nelson, P. A. & Arons, R. M.
open access

Advanced Fuel Cell Development Progress Report: October-December 1978

Description: Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes efforts directed toward understanding and improving the components of molten-carbonate-electrolyte fuel cells operated at temperatures near 925 K.
Date: June 1979
Creator: Finn, P. A.; Ackerman, J. P.; Pierce, R. D.; Nelson, P. A. & Arons, R. M.
open access

An Analytical Study of the Feasibility of Irradiating U233/Th232 Metal Fuel Experiments in EBR-II

Description: Recent concerns about the proliferation and diversion of plutonium have lead to reconsideration of Uranium-233/Thorium-232 fuel cycles. Although thorium fuels have been studied earlier, much of that work is incomplete; consequently, additional irradiation studies will be necessary.
Date: 1979?
Creator: Foltman, A. J. & Meneghetti, D.
open access

ARDISC (Argonne Dispersion Code): Computer Programs to Calculate the Distribution of Trace Element Migration in Partially Equilibrating Media

Description: A computer program (ARDISC, the Argonne Dispersion Code) is described which simulates the migration of nuclides in porous media and includes first order kinetic effects on the retention constants. The code allows for different absorption and desorption rates and solves the coupled migration equations by arithmetic reiterations. Input data needed are the absorption and desorption rates, equilibrium surface absorption coefficients, flow rates and volumes, and media porosities.
Date: April 1979
Creator: Strickert, Richard; Friedman, Arnold M. & Fried, Sherman
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Argonne National Laboratory Division of Biological and Medical Research, Annual Report: 1978

Description: Annual report of the Argonne National Laboratory Division of Biological and Medical Research summarizing research an other activities. This report includes studies related to nuclear energy, genetic effects of radiation, heavy metals, evaluation of effluents of fluidized bed combustion and coal gasification, electrical storage systems and energy transmittion, and development of population projection models.
Date: 1979?
Creator: Argonne National Laboratory. Division of Biological and Medical Research.
open access

Argonne National Laboratory Division of Biological and Medical Research, Annual Report: 1979

Description: Annual report of the Argonne National Laboratory Division of Biological and Medical Research summarizing research an other activities. This report includes studies related to nuclear energy include responses of beagles to continuous low-level 60Co gamma radiation, and development of indicators of leukemia; comparison of lifetime effects in mice of low-level neutron and 60Co gamma radiation; genetic effects of high LET radiations; and studies of the gastrointestinal absorption of the actinide e… more
Date: 1979?
Creator: Argonne National Laboratory. Division of Biological and Medical Research.
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Argonne National Laboratory Fuel Cycle Programs Progress Report: January-March, 1978

Description: Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research. This report includes fuel cycle studies in advanced solvent extraction techniques focused on development of centrifugal contactors for use in Purex processes and dispersion of liquids by explosions.
Date: April 1979
Creator: Steindler, M. J.; Ader, M.; Bernstein, G.; Flynn, K.; Gerding, T.; Jardine, L. J. et al.
open access

Argonne Solar Energy Program Annual Report: 1978

Description: Annual report of the Solar Energy Program describing work in solar energy collection, heating and cooling, thermal energy storage, ocean thermal energy conversion, photovoltaics, satellite power systems, bioconversion, central receiver solar thermal power, and wind energy conversion.
Date: February 1979
Creator: Argonne National Laboratory
open access

Biaxial Creep-Fatigue Behavior of Type 316H Stainless Steel Tube

Description: Biaxial creep-fatigue test data for Type 316 stainless steel tubes at 1100*Y are presented. The specimens were subjected to constant internal pressure and fluctuating axial strain with and without hold times in tension as well as compress ion. The results show that internal pressure significantly affects diametral ratchetting and axial stress range. Axial tensile hold is found to he more damaging than axial compressive hold even cinder a biaxial state of stress.
Date: April 1979
Creator: Majumdar, S.
open access

Calculations of Stresses in GCFR Cladding under Normal Operating Conditions

Description: A modified version of the LIFE-III code, LIFE-GCFR, and classical stress-analysis techniques have been used to calculate the stresses in the GCFR cladding under normal reactor operating conditions. Several types of loadings on the cladding that occur during normal operation have been considered. These include fuel-cladding mechanical interaction, thermal stresses induced by radial and axial temperature gradients, and swelling gradient-induced stresses. The combined and individual effects of the… more
Date: November 1979
Creator: Liu, Yung Y.; Hsieh, T. C. & Billone, Michael C.
open access

Chemical Engineering Division Fuel Cycle Programs Progress Report: April-June 1978

Description: Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research. This report includes studies on advanced solvent extraction techniques focused on the development of centrifugal contactors for use in Purex processes, extraction kinetics of ruthenium and zirconium in the presence of uranium, and dispersion of uranium and plutonium by fire… more
Date: December 1979
Creator: Steindler, M. J.; Ader, M.; Bernstein, G.; Flynn, K.; Gerding, T.; Jardine, L. J. et al.
open access

Critical Survey on Electrode Aging in Molten Carbonate Fuel Cells

Description: To evaluate potential electrodes for molten carbonate fuel cells, we reviewed the literature pertaining to these cells and interviewed investigators working in fuel cell technology. In this critical survey, the effect of three electrode aging processes - corrosion or oxidation, sintering, and poisoning - on these potential fuel-cell electrodes is presented. It is concluded that anodes of stabilized nickel and cathodes of lithium-doped NiO are the most promising electrode materials for molten ca… more
Date: December 1979
Creator: Kinoshita, K.
open access

The Current Status of Fusion Reactor Blanket Thermodynamics

Description: The available thermodynamic information is reviewed for three categories of materials that meet essential criteria for use as breeding blankets in deuterium-tritium (D-T) fueled fusion reactors: liquid lithium, solid lithium alloys, and lithium-containing ceramics. The leading candidate, liquid lithium, which also has potential for use as a coolant, has been studied more extensively than have the solid alloys or ceramics.
Date: April 1979
Creator: Veleckis, E.; Yonco, R. M. & Maroni, V. A.
open access

Design and Installation Manual for Thermal Energy Storage

Description: The purpose for this manual is to provide information on the design and installation of thermal energy storage in solar heating systems. It is intended for contractors, installers, solar system designers, engineers, architects, and manufacturers who intend to enter the solar energy business. The reader should have general knowledge of how solar heating systems operate and knowledge of construction methods and building codes. Knowledge of solar analysis methods such as f-chart, SOLCOST, DOE-1, o… more
Date: February 1979
Creator: Cole, Roger Lynn; Nield, Kenneth J.; Rohde, Raymond R. & Wolosewicz, R. M.
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Design of a System using CPC Collectors to Collect Solar Energy and to Produce Industrial Process Steam

Description: A system has been designed to use CPC collectors to collect solar energy and to generate steam for industrial process heat purposes. The system is divided into two loops with the collectors in the collector loop to operate a pre-heater and the collectors in the boiler loop to heat water to elevated pressures and temperatures. A flash boiler is used to throttle the heated water to steam. Two types of CPC collectors are chosen. In the collector loop the CPC collectors are fitted with concentric t… more
Date: August 1979
Creator: Argonne National Laboratory. Solar Energy Group.
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Development of a MK-II Loop to Simulate Reactor Hydraulic Conditions

Description: The Mk-IIC Integral Loop was modified to provide an in-pile experimental apparatus that would simulate the subassembly coolant flow rate and inlet pressure head of the Fast Test Reactor (FTR). There were two main design changes. First, the safety dump tanks were removed from the Mk-IIC loop and replaced by a second annular linear induction pump (ALIP). Second, a flow restricting orifice was sized so that the hydraulic requirements of prototypical test-section coolant velocity and pressure head … more
Date: January 1979
Creator: Page, R. J. & Robinson, L. E.
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Di-n-Amyl-n-Amylphosphonate and Tricaprylmethylammonium Nitrate as Potential Extractants for Reprocessing Th-U Fuels

Description: Both 2F di-n-amyl-n-amylphosphonate in n-dodecane (DA(AP)-DD) and 0.77F tricaprylmethylammonium nitrate in Aromatic 100 (TCMA.NO/sub 3/-AR100) extract uranium and thorium into relatively concentrated organic solutions. Countercurrent-flow tests with each extractant have demonstrated effective uranium-thorium separations by selective stripping from the organic phase. Both extractants offer advantageous alternatives to tributylphosphate (Thorex) in reprocessing irradiated mixed ThO2-UO2 fuels. Fo… more
Date: September 1979
Creator: Diamond, H.
open access

The Dynamic Response of Cracked Hexagonal Subassembly Ducts

Description: This report examines the dynamic elastic response of flawed and unflawed reactor subassembly ducts. A plane- strain finite-element analysis is presented for hexagonal ducts containing either internal corner cracks or external midflat cracks. Two geometric loading conditions are considered: uniform internal pressurization and point loads applied at opposite midflats. The time dependence of these loads was chosen as a Heaviside step function for the worst-case situation and as a triangular pulse … more
Date: April 1979
Creator: Glazik, J. L. & Petroski, H. J.
open access

Effects of Environment on the Low-Cycle Fatigue Behavior of Type 304 Stainless Steel

Description: The low-cycle fatigue behavior of Type 304 stainless steel has been investigated at 593 degrees C in a dynamic vacuum of better than 1.3 x 10⁻⁶ Pa (10⁻⁸ torr). The results concerning the effects of strain range, strain rate and tensile hold time on fatigue life are presented and compared with results of similar tests performed in air and sodium environments. Under continuous symmetrical cycling, fatigue life is significantly longer in vacuum than in air; in the low strain range regime, the effe… more
Date: December 1979
Creator: Argonne National Laboratory. Materials Science Division.
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