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open access

Advanced Fuel Cell Development Progress Report: January-March 1978

Description: Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes the development of electrolyte structures which have good electrolyte retention and mechanical properties as well as long term stability, and on developing methods of synthesis amenable to mass production.
Date: 1977?
Creator: Ackerman, J. P.; Ackerman, J. P.; Pierce, Robert Dean; Nelson, P. A.; Arons, R. M.; Kinoshita, K. et al.
open access

Alternative Fuel Cycle Options : Performance Characteristics and Impact on Nuclear Power Growth Potential

Description: The fuel utilization characteristics for LWR, SSCR, CANDU and LMFBR reactor concepts are quantified for various fuel cycle options, including once-through cycles, thorium cycles, and denatured cycles. The implications of various alternative reactor deployment strategies on the long-term nuclear power growth potential are then quantified in terms of the maximum nuclear capacity that can be achieved and the growth pattern over time, subject to the constraint of a fixed uranium-resource base. The … more
Date: September 1977
Creator: Chang, Y. I.; Till, C. E.; Rudolph, R. R.; Deen, J. R. & King, M. J.
open access

Analysis of EBR-II Low-Power Dosimetry Run 78C

Description: This report compares calculated reaction rates based on neutron-transport calculations in RZ and XY geometries with measured values from a low-power dosimetry test in EBR-II. Axial distributions of Uranium-235 and uranium-238 fission rates and uranium-238 capture rate are given for various radial locations along the length of the core and the axial reflectors, and along the length of the radial steel reflectors. Reaction rates, primarily at the reactor midplane, are given for a number of fissi… more
Date: December 1977
Creator: Franklin, F. C.; Ebersole, E. R. & Heinrich, R. R.
open access

An Analysis of the High-Temperature Particulate Collection Problem

Description: Particulate agglomeration and separation at high temperatures and pressures are examined, with particular emphasis on the unique features of the direct-cycle application of fluidized-bed combustion. The basic long-range mechanisms of aerosol separation are examined, and the effects of high temperature and high pressure on usable collection techniques are assessed. Primary emphasis is placed on those avenues that are not currently attracting widespread research. The high-temperature, particulate… more
Date: October 1977
Creator: Razgaitis, Richard
open access

Application of the Pulsed-Neutron Activation Technique for Flow Measurements at EBR-II

Description: This report describes the pulsed-neutron-activation (PNA) flow-measuring technique as applied to in situ fluid-flow measurement at EBR-II. Analytic relationships are derived for modeling the process and estimating the uncertainty in measurement. Results from measurements of both water flow and secondary-sodium flow are presented. Results from PNA measurements of water side of the EBR-II steam system have led better definition of plant parameters. Results from sodium-flow measurements are used t… more
Date: November 1977
Creator: Price, C. C.; Sackett, J. I.; Curran, R. N.; Livengood, C. L.; Kehler, P. & Forster, G. A.
open access

Autoradiographic Technique for Rapid Inventory of Plutonium-Containing Fast Critical Assembly Fuel

Description: A nondestructive autoradiographic technique is described which can provide a verification of the piece count and the plutonium content of plutonium-containing fuel elements. This technique uses the spontaneously emitted gamma rays from plutonium to form images of fuel elements on photographic film. Autoradiography has the advantage of providing an inventory verification without the opening of containers or the handling of fuel elements. Missing fuel elements, substitution of nonradioactive mate… more
Date: October 1977
Creator: Brumbach, S. B. & Perry, R. B.
open access

Biaxial Creep Behavior of Ribbed GCFR Cladding at 650 degrees C in Nominally Pure Helium (99. 99%)

Description: Biaxial creep-rupture tests were conducted on 12 prototypic GCFR fuel-cladding specimens at 650 deg C and a nominal hoop stress of 241.3 MPa. All test specimens were fabricated from 20% cold-worked Type 316 stainless steel tubes that were ribbed on the outer surface by mechanical grinding or electro-chemical etching. Test variables included specimen length and the presence or absence of weld-reinforcing end collars.
Date: November 1977
Creator: Yaggee, F. L.; Purohit, A.; Grajek, W. J. & Poeppel, R. B.
open access

Bilinear Cyclic Stress-Strain Analysis for Incoloy 800

Description: This report describes the bilinear stress-strain analysis under cyclic loading conditions for the alloy Incoloy 800. Although the method for determining the bilinear stress-strain parameters is based on a procedure proposed in the RDT Standard F9-1 for inelastic analysis of Fast Flux Test Facility (FFTF) components, the accuracy and consistency of results have been improved by an analytical technique, which also resulted in certain simplifications. The bilinear stress-strain parameters of solut… more
Date: 1977?
Creator: Maiya, P. S.
open access

Bubble Dynamics in a Superheated Liquid

Description: This report presents an extensive literature survey on bubble dynamics. Growth of a single spherical bubble moving in a uniformly superheated liquid is considered. Equations of motion and energy are presented in the forms that take into consideration the interaction between the motion and the growth. The fourth-order Runge-Kutta method is used to obtain a simultaneous solution of equations of motion and growth rate, and the solution is compared with available experimental results. Results for l… more
Date: September 1977
Creator: Sha, William T. & Shah, V. L.
open access

Chemical Engineering Division Sodium Technology Annual Report: July 1975-June 1976

Description: The Sodium Technology program currently comprises three parts. The first part is aimed at developing a model for accurately describing the behavior of tritium in LMFBRs from its formation in the core to its ultimate retention in the cold traps or release to the environment. Two important parts of this model are the behavior of the sodium cold traps and permeation of tritium through the steam-generator heat-transfer surfaces. A tritium monitor has been developed and installed on EBR-II to measur… more
Date: January 1977
Creator: McPheeters, C. C.; Jardine, L. J.; McKee, J. M.; Raue, D. J.; Renner, T. A.; Skladzien, S. B. et al.
open access

Cladding Failure by Local Plastic Instability

Description: Cladding failure is one of the major considerations in analysis of fuel-pin behavior during hypothetical accident transients since time, location, and nature of failure govern the early post-failure material motion and reactivity feedback. Out-of-pile thermal transient tests of both irradiated and unirradiated fast-reactor cladding show that local plastic instability, or bulging, often precedes rupture and that the extent of local instability limits the initial rip length. To investigate the de… more
Date: December 1977
Creator: Kramer, J. M. & Deitrich, L. W.
open access

Coal Liquefaction Support Studies

Description: A development program is being carried out to obtain information applicable to the SYNTHOIL process for converting coal to liquid fuel of low sulfur content. This report presents information on (1) the design of a calorimeter to measure heat of reaction of hydrogen with coal slurries, (2) the design of apparatus and calculations for measuring coefficients of heat transfer from SYNTHOIL process feed and effluent products to process vessel walls, (3) tests on the use of additives to facilitate th… more
Date: 1977?
Creator: Fischer, J.; Bump, T. R.; Mulcahey, T. P.; Jonke, A. A.; Lo, R.; Nandi, S. et al.
open access

Coal Liquefaction Support Studies

Description: A development program is being carried out to obtain information applicable to the SYNTHOIL process for converting coal to liquid fuel of low sulfur content. This report presents information on (1) the design of a calorimeter to measure heat of reaction of hydrogen with coal slurries, (2) the design of apparatus and calculations for measuring coefficients of heat transfer from SYNTHOIL process feed and effluent products to process vessel walls, (3) tests on the use of additives to facilitate th… more
Date: 1977?
Creator: Fischer, J.; Bump, T. R.; Mulcahey, T. P.; Jonke, A. A.; Lo, R.; Nandi, S. et al.
open access

Comparative Test Results for Two ODE Solvers: EPISODE and GEAR

Description: This is a sequel to the paper ''A comparison of two ODE codes: GEAR and EPISODE,'' and is concerned with the testing of two superficially similar ODE packages, GEAR and EPISODE. Fourteen basic test problems, some with several cases, are the basis for the testing. These problems represent several types-nonlinear systems with real and complex eigenvalues, linear systems with varied diagonal dominance, linear scalar problems, stiff and non-stiff problems, chemical kinetics with and without diurnal… more
Date: March 1977
Creator: Byrne, G. D.; Hindmarsh, A. C.; Jackson, Kenneth R. & Brown, H. Gordon
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

Comparisons of Finite-Element Code Calculations to Hydrostatically Loaded Subassembly-Duct Experiments

Description: The Liquid Metal Fast Breeder Reactor (LMFBR) core structure consists of a matrix of hexagonal subassembly ducts. Evaluation of the safety aspects of the core structure requires that reliable computational procedures be available to predict the deformation response of the subassembly configuration to postulated local energy releases. Finite-element computer codes have been developed to calculate deflections and strains of a hexcan subassembly wrapper subjected to internal and external dynamic p… more
Date: January 1977
Creator: Ash, J. E. & Marciniak, T. J.
open access

Computation of the Weight Function from a Stress Intensity Factor

Description: A simple representation for the crack-face displacement is employed to compute a weight function solely from stress intensity factors for a reference loading configuration. Crack face displacements given by the representation are shown to be in good agreement with analytical results for cracked tensile strips, and stress intensity factors computed from the weight function agree well with those for edge cracks in half planes, radial cracks from circular holes, and radially cracked rings. The tec… more
Date: October 1977
Creator: Petroski, H. J. & Achenbach, J. D.
open access

Conference on High Temperature Sciences Related to Open-Cycle, Coal-Fired MHD Systems : Argonne National Laboratory, Argonne, Illinois, April-4-6, 1977

Description: This conference was organized to identify, encourage, and promote greater understanding through basic research of the problems encountered in open-cycle, coal-fired MHD generators. The development of this system presents many challenging areas of research in materials sciences, thermodynamics, kinetics, solid state and ion-molecule chemistry and physics, all focused on phenomena occurring at high temperature. The scope of the conference has been designed to improve interdisciplinary communicat… more
Date: 1977?
Creator: Thorn, R. J.
open access

Considerations Affecting Deep-Well Disposal of Tritium-Bearing Low-Level Aqueous Waste from Nuclear Fuel Reprocessing Plants

Description: Present concepts of disposal of low-level aqueous wastes (LLAW) that contain much of the fission-product tritium from light water reactors involve dispersal to the atmosphere or to surface streams at fuel reprocessing plants. These concepts have been challenged in recent years. Deep-well injection of low-level aqueous wastes, an alternative to biospheric dispersal, is the subject of this presentation. Many factors must be considered in assessing its feasibility, including technology, costs, env… more
Date: March 1977
Creator: Trevorrow, L. E.; Warner, D. L. & Steindler, M. J.
open access

Cs--U--O Phase Diagram and its Application to Uranium--Plutonium Oxide Fast Reactor Fuel Pins

Description: Portions of the cesium-uranium-oxygen system have been investigated between 873 and 1273°K and a phase diagram has been constructed using our data and the data of other workers in the field. Thermodynamic and kinetic data have been used to examine the reactions that occur in fast-reactor fuel pins between fission-product cesium and the uranium oxide blanket. It was concluded that at the low oxygen potentials existing at the interface between the uranium-plutonium mixed-oxide and the uranium oxi… more
Date: August 1977
Creator: Davis, S. A.; Johnson, C. E.; Johnson, I.; Fee, D. C.; Shinn, W. A. & Staahl, G.
open access

Cyclic-Deformation Resistance of Weld-Deposited Type 16-8-2 Stainless Steel at 593 Degrees C

Description: This report presents results from an investigation on the creep-fatigue and cyclic-deformation of Type 16-8-2 (16% Cr-8% Ni-2% Mo) stainless steel weld metal. Tests were conducted in air at 593 degrees C and a strain rate of 0.004 s⁻¹. Comparisons with data for Type 316 stainless steel base metal indicated that the weld metal has significantly longer fatigue lives for several tension hold-time tests. This is attributed to the fine duplex microstructure of the weld metal that inhibits the growth… more
Date: August 1977
Creator: Raske, D. T.
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