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PTOLEMY, a Program for Heavy-Ion Direction-Reaction Calculations

Description: Ptolemy is an IBM/360 program for the computation of nuclear elastic and direct-reaction cross sections. It carries out both optical-model fits to elastic-scattering data at one or more energies, and DWBA calculations for nucleon-transfer reactions. Ptolemy has been specifically designed for heavy-ion calculations. It is fast and does not require large amounts of core. The input is exceptionally flexible and easy to use. This report outlines the types of calculation that Ptolemy can carry out, … more
Date: March 1976
Creator: Gloeckner, D. H.; Macfarlane, M. H. & Pieper, Steven C.
Partner: UNT Libraries Government Documents Department
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Computer-Code Formulation for Three-Dimensional HEXCAN Response Coupled with Internal Hydrodynamics

Description: A procedure is described for the dynamic analysis of a fast-reactor hexagonal subassembly. The internals of the fuel subassembly are treated by an axisymmetric hydrodynamic code REXCO-HT which, among other properties, possesses a model of an MFCI pressure source. The housing of the fuel subassembly is handled by the SADCAT code, which is based on a triangular finite element in three-dimensional space. The code is used to illustrate the discrepancies involved if the hexcan is modeled by a cylind… more
Date: March 1976
Creator: Marchertas, A. H. & Julke, R. T.
Partner: UNT Libraries Government Documents Department
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Study on Flow Instabilities in Two-Phase Mixtures

Description: Various mechanisms that can induce flow instabilities in two-phase flow systems are reviewed and their relative importance discussed. In view of their practical importance, the density-wave instabilities have been analyzed in detail based on the one-dimensional two-phase flow formulation. The dynamic response of the system to the inlet flow perturbations has been derived from the model; thus the characteristic equation that predicts the onset of instabilities has been obtained. The effects of v… more
Date: March 1976
Creator: Ishii, M.
Partner: UNT Libraries Government Documents Department
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Explosive Interaction of Molten UO2 and Liquid Sodium

Description: The interim report presented describes a continuation of the work reported in ANL-7890, Interaction of Sodium with Molten Uranium dioxide and Stainless Steel Using a Dropping Mode of Contact. In the current study, sodium was injected into a pool of molten uranium dioxide. The experiment consistently produced vapor explosions, both with the injection nozzle above and beneath the surface of the uranium dioxide. Although the efficiency of the conversion of thermal to mechanical energy was small (d… more
Date: March 1976
Creator: Armstrong, D. R.; Goldfuss, G. T. & Gebner, R. H.
Partner: UNT Libraries Government Documents Department
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Xenon-Tagging in Production of EBR-II Mark II Driven-Fuel Elements

Description: About 1200 Mark II driver-fuel elements were xenon-tagged to facilitate qualification for irradiation of Mark II fuel manufactured at ANL-West. Tagging equipment was designed and developed. In this equipment, the plenum in a fuel-element jacket was evacuated then filled with xenon to a predetermined pressure. The equipment design allows tagging and element fabrication to proceed normal rates for production of fuel elements. A Kr-85 tracer in the xenon-tag gas verified by gamma counting the adeq… more
Date: March 1976
Creator: Wilkes, C. W.; Ryan, M. J.; Laug, M. T. & Fryer, R. M.
Partner: UNT Libraries Government Documents Department
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Plutonium Safety Training Course

Description: This course seeks to achieve two objectives: to provide initial safety training for people just beginning work with plutonium, and to serve as a review and reference source for those already engaged in such work. Numerous references have been included to provide information sources for those wishing to pursue certain topics more fully. The first part of the course content deals with the general safety approach used in dealing with hazardous materials. Following is a discussion of the four prope… more
Date: March 1976
Creator: Moe, H. J.
Partner: UNT Libraries Government Documents Department
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Final Safety Analysis Addenda to Hazards Summary Report, Experimental Breeder Reactor II (EBR-II) : Upgrading of Plant Protection System, Volume 1

Description: This report is a compilation of the formal Final Safety Analysis Addenda (FSAA's) to the EBR-II Hazard Summary Report and Addendum that have been prepared in support of certain modifications to the reactor-shutdown-system portion of the EBR-II plant protection system. Each major section is an edited version of the original FSAA for a particular modification and provides a description of the pre - and post -modification system, the rationale for the modification, and required supporting safety a… more
Date: March 1976
Creator: Sackett, J. I. & Gale, N. L.
Partner: UNT Libraries Government Documents Department
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One-Dimensional Cladding-Relocation Model for Fast-Reactor Loss-of-Flow Accidents

Description: The motion and location of the molten-cladding during an unprotected loss-of-flow accident in liquid metal fast breeder reactors are important because of the effects on the reactivity and the subsequent fuel motion. The present study analyzes the cladding-relocation problem based on a single-channel film-flow model and a simple thermal transient model for fuel pins. The motion of molten cladding induced by sodium-vapor streaming undergoes initial rapid upward acceleration, slowing down, flow re… more
Date: March 1976
Creator: Ishii, M.; Chen, W. L. & Grolmes, M. A.
Partner: UNT Libraries Government Documents Department
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Experimental and Analytical Study of the Sputtering Phenomena

Description: An experimental apparatus was constructed to examine the heat-transfer characteristics of a sputtering front. In the present study, a heat source of sufficient intensity was located immediately below the sputtering front, which prevented its downward progress, thus permitting detailed measurements of steady-state surface temperatures throughout a sputtering front. A two-dimensional analytical model was developed to describe a stationary sputtering front where the wet-dry interface corresponds t… more
Date: March 1976
Creator: Howard, Paul A.
Partner: UNT Libraries Government Documents Department
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Comparison of the AMDAHL 470V/6 and the IBM 370/195 Using Benchmarks

Description: Six groups of jobs were run on the IBM 370/195 at the Applied Mathematics Division (AMD) of Argonne National Laboratory using the current production versions of OS/MVT 21.7 and ASP 3.1. The same jobs were then run on an AMDAHL 470V/6 at the AMDAHL manufacturing facilities in Sunnyvale, California, using the identical operating systems. Performances of the two machines are compared. Differences in the configurations were minimized. The memory size on each machine was the same, all software which… more
Date: March 1976
Creator: Snider, D. R.; Midlock, J. L.; Hinds, A. R. & Engert, D. E.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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Advanced Fuel Cell Development Progress Report: October-December 1977

Description: Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes work aimed at understanding and improving the performance of fuel cells having molten alkali-carbonate mixtures as electrolytes; the fuel cells operate at temperatures near 925 K.
Date: March 1978
Creator: Ackerman, J. P.; Kinoshita, K.; Finn, P. A.; Sim, J. W. & Nelson, P. A.
Partner: UNT Libraries Government Documents Department
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Physics of Reactor Safety, Quarterly Report: October-December 1977

Description: Quarterly progress report summarizing work done in Argonne National Laboratory's Applied Physics Division and Components Technology Division. The work in the Applied Physics Division includes reports on reactor safety program by members of the Reactor Safety Appraisals Group, Monte Carlo analysis of safety-related critical assembly experiments by members of the Theoretical Fast Reactor Physics Group, and Planning of Safety-Related (ZPR) Planning and Experiments Group. Work on reactor core therm… more
Date: March 1978
Creator: Argonne National Laboratory. Applied Physics Division.
Partner: UNT Libraries Government Documents Department
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Light-Water-Reactor Safety Research Program Quarterly Progress Report: October-December 1976

Description: Quarterly progress report summarizing work performed by the Argonne National Laboratory Light-Water-Reactor Safety Research Program. It includes sections discussing research and development in: (1) loss of-coolant accident research: heat transfer and fluid dynamics; (2) transient fuel response and fission-product release program; (3) mechanical properties of zircaloy containing oxygen; and (4) steam-explosion studies.
Date: March 1977
Creator: Sachs, Robert G. & Kyger, Jack A.
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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Physics of Reactor Safety, Quarterly Report: October-December 1976

Description: Quarterly progress report summarizing work done in Argonne National Laboratory's Applied Physics Division including: reactor safety research and technical coordination of the Reactor Safety Research safety analysis program.
Date: March 1977
Creator: Argonne National Laboratory. Applied Physics Division.
Partner: UNT Libraries Government Documents Department
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The Status and Development Potential of Plate-Type Fuels for Research and Test Reactors

Description: A program of transient in-reactor experiments is being conducted by Argonne National Laboratory in the Transient Reactor Test (TREAT) facility to guide and support analyses of hypothetical core-disruptive accidents (HCDA) in liquid-metal fast breeder reactors (LMFBR). Test results provide data needed to establish the response of LMFBR cores to hypothetical accidents producing fuel failure, coolant boiling, and the movement of coolant, molten fuel, and molten cladding. These data include margins… more
Date: March 1979
Creator: Stahl, D.
Partner: UNT Libraries Government Documents Department
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Nondestructive Evaluation Techniques for Silicon Carbide Heat-Exchanger Tubes : Annual Report, October 1977-September 1978

Description: This report discusses the adequacy of several nondestructive evaluation techniques for the detection of flaws in silicon carbide heat-exchanger tubing. Experimental results have been obtained for conventional ultrasonic testing, acoustic microscopy, conventional and dye-enhanced radiography, holographic interferometry, infrared scanning and internal-friction measurements.
Date: March 1979
Creator: Kupperman, D. S.; Yuhas, D.; Sciammarella, Cesar A.; Lapinski, N. P. & Fiore, N. F.
Partner: UNT Libraries Government Documents Department
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Studies of Nuclear Waste Migration in Geologic Media, Annual Report: November 1976-October 1977

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 confinement of nuclear waste in geologic formations as a method of permanently disposing of the waste.
Date: March 1978
Creator: Argonne National Laboratory. Chemical Engineering Division.
Partner: UNT Libraries Government Documents Department
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