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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.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
open access

Finite-Element Method for Above-Core Structures

Description: Three-dimensional finite-element models for the treatment of the nonlinear, transient response of a fast breeder reactor's above-core structures are described. For purposes of treating arbitrarily large rotations, node orientations are described by unit vectors and the deformable elements are treated by a corotational formulation in which the coordinate system is embedded in the elements. Deformable elements may be connected either to nodes directly or through rigid bodies. The time integration… more
Date: December 1979
Creator: Kennedy, J. M. & Belytschko, Ted B.
Item Type: Refine your search to only Report
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A Quasi-Eulerian Method for Analyzing Slug Impact and Coolant Spillage in a Fast-Reactor Accident

Description: This report describes a quasi-Eulerian method which has been incorporated into the ICECO code to study slug impact and coolant spillage problems in a fast-reactor accident. The quasi-Eulerian cells used in this method are located on the tops of the regular cells. The axial size of the quasi-Eulerian cells varies according to the gap generated at the reactor head-wall junction. Penetration holes on the cover head are modeled on the top center of the quasi-Eulerian cells. Fluid variables in these… more
Date: December 1979
Creator: Chu, Han Y.
Item Type: Refine your search to only Report
open access

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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
open access

Materials Technology for Coal-Conversion Processes Quarterly Report: April-June 1979

Description: Quarterly report on the activities of the Argonne National Laboratory Materials Science Division regarding economical conversion of coal into clean and usable fuels through the use of durable materials systems. This project is designed to provide part of the materials information necessary for successful operation of coal-conversion systems.
Date: November 1979
Creator: Argonne National Laboratory. Materials Science Division.
Item Type: Refine your search to only Report
open access

Nondestructive Evaluation Techniques for Silicon Carbide Heat-Exchanger Tubes : Second Annual Report, October 1978-September 1979

Description: This report discusses the development of ultrasonic testing, acoustic microscopy, dye-enhanced radiography, holographic interferometry, and infrared scanning techniques for flaw detection in silicon carbide (SiC) heat-exchanger tubing. Both preservice and in-service testing requirements are discussed. An ultrasonic boreside probe and an acoustic microscope stage have been designed for continuous monitoring of SiC tubing. Preliminary results with these acoustic systems are presented. In addition… more
Date: November 1979
Creator: Kupperman, D. S.; Yuhas, D.; Deininger, W. & Sciammarella, Cesar A.
Item Type: Refine your search to only Report
open access

Laser Microsampling Method for Determination of Retained Fission Gas in Irradiated Nuclear Fuels

Description: A small ruby laser adapted to fire through a microscope is used to release fission gases from specific sites on a plane surface of an irradiated fuel specimen. Interaction of the focused laser pulse with the specimen surface results in a conical crater from which sampled material has been vaporized; the crater is surrounded by a heat-affected zone in which intergranular fracture and grain separation allow release of grain-boundary gases. Procedures for measuring the amount of krypton-85 release… more
Date: October 1979
Creator: Graczyk, D. G.; Bandyopadhyay, G.; Gehl, S. M.; Hughes, J. P. & Goodspeed, H. T.
Item Type: Refine your search to only Report
open access

LIMBO Computer Code for Analyzing Coolant-Voiding Dynamics in LMFBR Safety Tests

Description: The LIMBO (liquid metal boiling) code for the analysis of two-phase flow phenomena in an LMFBR reactor coolant channel is presented. The code uses a non-equilibrium, annular, two-phase flow model, which allows for slip between the phases. Furthermore, the model is intended to be valid for both quasi-steady boiling and rapid coolant voiding of the channel. The code was developed primarily for the prediction of, and the posttest analysis of, coolant-voiding behavior in the SLSF P-series in-pile s… more
Date: October 1979
Creator: Bordner, G. L.
Item Type: Refine your search to only Report
open access

Mechanical Properties Test Program on Structural Materials in a Sodium Environment

Description: This document describes in detail the ongoing and planned US Test program on the mechanical properties of sodium-exposed Type 316 austenitic stainless and Fe-2 1/4 Cr-1 Mo ferritic steels. The test program is based on the Development Requirement Specifications (DRS) established by the DOE/Clinch River Breeder Reactor Project (CRBRP) Program Office, the general need for the development of LMFBR structural-design criteria established by the Nuclear Systems Materials Handbook, and the need for a f… more
Date: October 1979
Creator: Natesan, K.; Chopra, O. K. & Kassner, T. F.
Item Type: Refine your search to only Report
open access

Numerical Method for Solution of Transient, Homogeneous, Equilibrium, Two-Phase Flows in One Space Dimension

Description: This report presents a solution method for transient, homogeneous, equilibrium, two-phase flows of a single-component fluid in one space dimension. The method combines a direct finite-difference procedure and the method of characteristics. The finite-difference procedure solves the interior points of the computing domain; the boundary information is provided by a separate procedure based on the characteristics theory. The solution procedure for boundary points requires information in addition t… more
Date: October 1979
Creator: Shin, Yong W. & Wiedermann, Arne H.
Item Type: Refine your search to only Report
open access

Unavailability Modeling and Analysis of Redundant Safety Systems

Description: Analytical expressions have been developed to estimate the average unavailability of an m-out-of-n (m/n, 1 less than or equal to m less than or equal to n less than or equal to 4) standby safety system of a nuclear power plant. The expressions take into account contributions made by testing, repair, equipment failure, human error, and different testing schemes. A computer code, ICARUS, has been written to incorporate these analytical equations. The code is capable of calculating the average una… more
Date: October 1979
Creator: Argonne National Laboratory. Reactor Analysis and Safety Division.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
open access

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.
Item Type: Refine your search to only Report
open access

Review and Analysis of Spray Combustion as Related to Alternative Fuels

Description: A review was conducted during the period of mid-June to mid-August 1979, of the literature on spray combustion. Particular attention has been paid to theoretical and experimental work on droplet and spray combustion applicable to the use of alternate fuels, mainly liquid fuels derived from coal and shale.
Date: September 1979
Creator: Black, C. H.; Chiu, H. H.; Fischer, J. & Clinch, J. M.
Item Type: Refine your search to only Report
open access

Studies of Nuclear Waste Migration in Geologic Media, Annual Report: October 1978-September 1979

Description: Annual report of the Argonne National Laboratory Chemical Engineering Division regarding studies of nuclear waste migration in geologic media. This report discusses research regarding nuclide migration by fluid flow in rock.
Date: September 1979
Creator: Seitz, M. G.; Rickert, P. G.; Couture, R. A.; Williams, J.; Meldgin, N.; Fried, Sherman M. et al.
Item Type: Refine your search to only Report
open access

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.
Item Type: Refine your search to only Report
open access

Feasibility of Underground Storage/Disposal of Noble Gas Fission Products

Description: The quantities of krypton-85 that can be released to the environment from nuclear energy production are to be limited after 1983 by Federal regulations. Although procedures for collecting the krypton-85 released in the nuclear fuel cycle have been developed to the point that they are commercially available, procedures for terminal disposal of the collected gas are still being examined for their feasibility. In this work, the possibilities of underground disposal of krypton-85 by several techniq… more
Date: August 1979
Creator: Winar, R. M.; Trevorrow, L. E. & Steindler, M. J.
Item Type: Refine your search to only Report
open access

Multichannel Clad-Relocation Model for Fast-Reactor Loss-of-Flow Accidents

Description: During an unprotected undercooling accident in a liquid-metal fast breeder reactor, the motion and relocation of the molten cladding can he important because of its potentially significant effect on reactivity, blockage formation, and subsequent fuel motion. The present study analyzes the clad relocation problem1 based on a multichanneI film-flow model. The important aspects considered in the analysis are the nonuniform transverse ci1ad-melting pattern and diversions of sodium vapor flow within… more
Date: August 1979
Creator: Ishii, M.; Chen, W. L. & Grolmes, M. A.
Item Type: Refine your search to only Report
open access

Recovery of Actinides from TBP-Na₂CO₃ Scrub-Waste Solutions: the ARALEX Process

Description: A flow-sheet for the recovery of actinides from TBP-Na2CO3scrub-waste solutions has been developed, based on batch extraction data, and tested, using laboratory-scale countercurrent extraction techniques. The process, called the ARALEX process, uses 2-ethyl-1-hexanol (2-EHOH) to extract the TBP degradation products (HDBP and H/sub 2/MBP) from acidified Na2CO3scrub waste leaving the actinides in the aqueous phase. Dibutyl and monobutyl phosphoric acids are attached to the 2-EHOH molecules throug… more
Date: August 1979
Creator: Horwitz, E. P.; Bloomquist, C. A. A.; Mason, G. W.; Leonard, R. A. & Ziegler, A. A.
Item Type: Refine your search to only Report
open access

The Wetting Behavior of Molten-Chloride Electrolytes: Capillarity Effects in Lithium-Aluminum/Metal Sulfide Batteries

Description: A lithium-aluminum/iron sulfide battery which uses a molten LiCl-KCl electrolyte is presently under development at Argonne National Laboratory. The performance and lifetime of this electrochemical system depend, in part, on the ability of the electrolyte to wet the materials used as electrodes, separators, and particle retainers. For this reason contact-angle measurements were made on smooth, 100%-dense surfaces of the cell materials. In addition, electrolyte penetrability determinations were m… more
Date: August 1979
Creator: Eberhart, James G.
Item Type: Refine your search to only Report
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