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open access

Final Report on the Small-Scale Vapor-Explosion Experiments Using a Molten NaCl-H2O System

Description: Vapor explosions were produced by injecting small quantities of water into a container filled with molten sodium chloride. Minimum explosion efficiencies, as evaluated from reaction-impulse measurements, were relatively large. Subsurface movies showed that the explosions resulted from a two-step sequence: an initial bulk-mixing phase in which the two liquids intermix on a large scale, but remain locally separated by an insulating gas-vapor layer; and a second step, immediately following breakdo… more
Date: April 1976
Creator: Anderson, R. P. & Bova, L.
open access

Survey and Status Report on Application of Acoustic-Boiling-Detection Techniques to Liquid-Metal-Cooled Reactors

Description: Report issued by the Argonne National Laboratory discussing acoustic-boiling-detection techniques. As stated in the abstract, "this report summarizes literature through June 1967 concerning acoustic methods. In the acoustic method for boiling detection, either acoustic waveguides or high-temperature acoustic sensors are recommended" (p. 1). This report includes tables, and illustrations.
Date: April 1970
Creator: Anderson, T. T.; Mulcahey, T. P. & Hsu, C.
open access

A Residential Energy Consumption Analysis Utilizing the DOE-1 Computer Program

Description: The DOE-1 computer program under development by Argonne National Laboratory, Lawrence Berkeley Laboratory, and Los Alamos Scientific Laboratory is used to examine energy consumption in a typical middle-class household in Cincinnati, Ohio. The program is used to compare energy consumption under different structural and environmental conditions including various levels of insulation in the walls and ceiling, double and single glazing of windows, and thermostat setback schedules.
Date: April 1979
Creator: Arentsen, Scott K.
open access

Community Systems Program: Its Goals and Accomplishments, 1978

Description: The Community Systems Program is concerned with conserving energy and scarce fuels through new methods of satisfying the energy needs of American communities. These programs are designed to develop innovative ways of combining current, emerging, and advanced technologies into Integrated Community Energy Systems (ICES) that could furnish any, or all, of the energy-using services of a community. The key goals of the Community System Program then, are to identify, evaluate, develop, demonstrate, a… more
Date: April 1978
Creator: Argonne National Laboratory
open access

Simple Conduction Model with Phase Change for Fuel Pin

Description: A simple conduction model with phase change has been developed for the transient analysis of a fuel pin based on average properties and lumped-parameter techniques. The transient behavior of fuel and cladding can be accurately described by simple analytical expressions that agree with conventional numerical approaches for under-cooling transient analysis. If it be assumed that the heat-transfer resistance between the fuel and cladding remains the same for both steady-state and transient periods… more
Date: April 1976
Creator: Chen, W. L.; Ishii, M. & Grolmes, M. A.
open access

Engineering Analysis of Thermal Phenomena for Lead-Acid Batteries During Recharge Processes

Description: Transient thermal phenomena in Pb/PbO2 (lead-acid) batteries during charging processes were investigated. Mathematical models were formulated for the studies of heat transfer behavior across the electrode/electrolyte interface within a porous PbO2 electrode during charging, thermal behavior and temperature distribution over a lead-acid battery during different charging processes designed for electric-vehicle propulsion application, and cooling methods for lead-acid batteries during recharge cyc… more
Date: April 1977
Creator: Choi, K. W. & Yao, N. P.
open access

Final Report of Fuel Dynamics Test E7

Description: Test data from an in-pile failure experiment of high-power LMFBR-type fuel pins in a simulated $3/s transient-overpower (TOP) accident are reported and analyzed. Major conclusions are that (1) a series of cladding ruptures during the 100-ms period preceding fuel release injected small bursts of fission gas into the flow stream; (2) gas release influenced subsequent cladding melting and fuel release (there were no measurable FCI's (fuel-coolant interactions), and all fuel motion observed by the … more
Date: April 1977
Creator: Doerner, R. C.; Murphy, W. F.; Stanford, G. S. & Froehle, P. H.
open access

Final Safety Analysis Addendum to Hazard Summary Report, Experimental Breeder Reactor No. II (EBR-II): the EBR-II Cover-Gas Cleanup System

Description: This report evaluates abnormal and accident conditions postulated for the EBR-II cover-gas cleanup system (CGCS). Major considerations include loss of CGCS function with a high level of cover-gas activity, loss of the liquid-nitrogen coolant required for removing fission products from the cover gas, contamination of the cover gas from sources other than the reactor, and loss of system pressure boundary. Calculated exposures resulting from the maximum hypothetical accident (MHA) are less than 2%… more
Date: April 1979
Creator: Fryer, R. M.; Monson, L. R.; Price, C. C. & Hooker, D. W.
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

Studies of Unprotected Loss-of-Flow Accidents for the Clinch River Breeder Reactor

Description: Studies of unprotected loss-of-flow accidents in the CRBR for various rates of flow coast-down and with various options in the SAS 3A code did not lead to conditions for a violent disassembly. Maximum fuel temperatures using the SLUMPY module for disassembly were in the range 4000-4500 deg C. An approximate treatment of the LOF-driven TOP accident, not properly modeled by SAS 3A, indicates the possibility of some increase in accident severity. The effect of fission gas in dispersing fuel was no… more
Date: April 1976
Creator: Hummel, Harry H.; Pizzica, P. A. & Kalimullah
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

Fluidized-Bed Regeneration of Sulfated Dolomite from a Coal-Fired FBC Process by Reductive Decomposition

Description: A fluidized-bed, reductive decomposition process has been developed for regenerating calcium sulfate, a product of fluidized-bed combustion. The effect of process operating variables on the extent of regeneration and on the SO2 levels in the off-gas has been determined, and a process model has been proposed. A process for regenerating spent SO2 sorbents has been developed on a PDU scale. Tymochtee dolomite that had been sulfated during fluidized-bed combustion of coal is regenerated (reductive… more
Date: April 1977
Creator: Montagna, John C.; Vogel, Gerhard J.; Smith, Gregory W. & Jonke, Albert A.
open access

High-Performance Batteries for Off-Peak Energy Storage and Electric-Vehicle Propulsion, Progress Report: July-December 1975

Description: Progress report describing the research and management efforts of Argonne National Laboratory's program on high-performance lithium/metal sulfide batteries during the period July-December 1975. The batteries are being developed for two applications: off-peak energy storage in electric utility networks and electric-vehicle propulsion. The battery designs for the two applications differ, particularly in cell configuration and electrode design because of the differing performance requirements.
Date: April 1976
Creator: Nelson, P. A.; Ivins, R. O.; Yao, N. P.; Battles, J. E.; Chilenskas, A. A.; Gay, E. C. et al.
open access

Risk-assessment methodology for fast breeder reactors

Description: The methods applied or proposed for risk assessment of nuclear reactors are reviewed, particularly with respect to their applicability for risk assessment of future commercial fast breeder reactors. All methods are based on the calculation of accident consequences for relatively few accident scenarios. The role and general impact of uncertainties in fast-reactor accident analysis are discussed. The discussion shows the need for improvement of the methodology. A generalized and improved risk-ass… more
Date: April 1976
Creator: Ott, Karl O.
open access

Measurement of the Hydrogen Yield in the Radiolysis of Water by Dissolved Fission Products

Description: Hydrogen from the radiolysis of water by dissolved fission products is stripped from the solution and collected by bubbling carbon dioxide through the solution. Quantitative measurements of the G value for hydrogen show that the yield is essentially the same as would be obtained by external gamma radiolysis of nonradioactive solutions of the same chemical composition. The hydrogen yield can be enhanced by addition of a hydrogen-atom donor, such as formic acid, to the solution. The yield of hydr… more
Date: April 1976
Creator: Sauer, M. C., Jr.; Hart, E. J.; Flynn, K. F. & Gindler, J. E.
open access

HYCSOS : A Chemical Heat Pump and Energy Conversion System Based on Metal Hydrides

Description: The current status of the HYCSOS chemical heat pump and energy conversion system based on metal hydrides is described. Heat transfer fluid loops were insulated and modified for isothermal operation. Software development for HYCSOS manual mode operation was completed. Routines to handle data acquisition, logging, compression, correction and plotting, using a Tektronix Graphics system with flexible disk data storage, provide a rapid and versatile means of presenting HYCSOS data for analysis. Adva… more
Date: April 1979
Creator: Sheft, Irving; Gruen, Dieter M. & Lamich, George
open access

A Comparison of the IBM 370/168 MODEL 3 with the Amdahl 470V/6 and the IBM 370/195 Using Benchmarks

Description: As part of the studies preliminary to the acquisition of additional computing capability at Argonne National Laboratory, six groups of jobs were run on the IBM 370/195 at the Applied Mathematics Division of Argonne National Laboratory, on an Amdahl 470V/6 at the Amdahl manufacturing facilities in Sunnyvale, California, and on an IBM 370/168 MODEL 3 at the IBM Field Support Center in Gaithersburg, Maryland. This report compares the performance of the IBM 370/168 MOD 3 with that of the other two … more
Date: April 1977
Creator: Snider, D. R.; Midlock, J. L. & Hinds, A. R.
open access

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

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
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

Monte Carlo-Based Validation of the ENDF/MC²-II/SDX Cell Homogenization Path

Description: The results are presented of a program of validation of the unit cell homogenization prescriptions and codes used for the analysis of Zero Power Reactor (ZPR) fast breeder reactor critical experiments. The ZPR drawer loading patterns comprise both plate type and pin-calandria type unit cells. A prescription is used to convert the three dimensional physical geometry of the drawer loadings into one dimensional calculational models. The ETOE-II/MC²-II/SDX code sequence is used to transform ENDF/B … more
Date: April 1979
Creator: Wade, D. C.
open access

Waste Production and Management at EBR-II

Description: This report surveys waste production rates and disposal practices at EBR-II, a small-scale liquid-metal fast breeder reactor, for the past decade. Normal airborne wastes have been reduced by switching to low-sulfur fuel oil in auxiliary boilers and converting to use of reactor steam for part of the plant space heating. Atmospheric releases of gaseous radioactive wastes initially increased during the implementation of program for testing reactor fuels to and beyond cladding breach; but the efflu… more
Date: April 1979
Creator: Witbeck, L. C. & Fryer, R. M.
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