UNT Libraries Government Documents Department - 116 Matching Results

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SYN3D: a Single-Channel, Spatial Flux Synthesis Code for Diffusion Theory Calculations

Description: This report is a user's manual for SYN3D, a computer code which uses single-channel, spatial flux synthesis to calculate approximate solutions to two- and three-dimensional, finite-difference, multi-group neutron diffusion theory equations. SYN3D is designed to run in conjunction with any one of several one- and two-dimensional, finite-difference codes (required to generate the synthesis expansion functions) currently being used in the fast reactor community. The report describes the theory and… more
Date: 1976
Creator: Adams, C. H.
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Numerical Integration of Large Deflection Elastic-Plastic Axisymmetric Shells of Revolution

Description: The improvement in the method of large deflection elastic-plastic analysis of shells and other structures appears to have continued interest. With the development in this work an improved numerical suppression scheme is now available for the large deflection elastic-plastic analysis of axisymmetric shells of revolution subjected to symmetric loadings. Quasi-linearization of Sander's non-linear shell equations is presented for the first time. With these quasi-linearized equations the suppression… more
Date: December 1976
Creator: Ahmed, Habib Uddin
open access

An Overview of Pool-Type LMFBRs : General Characteristics

Description: This report describes the results of a study conducted by a "Pool Study Group" organized at ANL in mid-1975 to examine the present state of the air of design of pool-type LMFBRs. The study concentrated on examination of various design options used to date in the principle pool-type projects and design studies in this country and abroad, including the Phenix and Super-Phenix reactors (France), PFR and CFR (U.K.), RN-600 (U.S.S.R.) and EBR-II (U.S.A.). The objective of the report is to provide a … more
Date: May 1976
Creator: Amorosi, A.; Hutter, E.; Marciniak, T. J.; Monson, H. O.; Seidensticker, R. W. & Simmons, W. R.
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

Environmental Pollutants and the Urban Economy : Phase 1. Final Report, June 1972-October 1975

Description: Costs and benefits of various urban air pollution control policies have been examined in Phase 1 of the Environmental Pollutants and the Urban Economy study being conducted jointly by Argonne National Laboratory and the University of Chicago. The need for sound economic evaluation of air quality regulations is evidenced by the resistance of many industries to pollution control policies based solely on the technical feasibility of achieving public health-related standards. For many firms that em… more
Date: October 1976
Creator: Argonne National Laboratory
open access

Light-Water-Reactor Safety Research Program

Description: Progress report on water-reactor-safety heat-transfer and flow problems. Covering the following research and development areas: loss-of-coolant accident research, transient fuel response and fission-product release program, mechanical properties of zircaloy containing oxygen, and steam-expulsion studies.
Date: December 1976
Creator: Argonne National Laboratory
open access

Light-Water-Reactor Safety Research Program

Description: This progress report summarizes the Argonne National Laboratory work performed during April, May, and June 1976 on water-reactor-safety heat-transfer and flow problems. The following research and development areas are covered: (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: 1976?
Creator: Argonne National Laboratory
open access

Light-Water-Reactor Safety Research Program, Quarterly Progress Report: October-December 1975

Description: Quarterly report summarizing work by Argonne National Laboratory on water-reactor-safety heat-transfer and flow problems. "The following research and development areas are covered: (1) Loss-of-coolant Accident Research: Heat Transfer and Fluid Dynamics; (2) Transient Fuel Response and Fission-product Release Program; and (3) Mechanical Properties of Zircaloy Containing Oxygen" (p. x).
Date: 1976?
Creator: Argonne National Laboratory
open access

Materials Science Division Coal Technology Quarterly Report: April-June 1976

Description: Quarterly report of the Argonne National Laboratory Materials Science Division regarding coal technologyresearch and development. This report summarizes the work performed in six major tasks: evaluation of ceramic refractories, evaluation of ceramic coatings and refractories, development of nondestructive testing methods for use in coal plant fabrication, development of computer models to predict corrosion behavior, computer models to predict erosion behavior, and analysis of pilot-plant compo… more
Date: 1976?
Creator: Argonne National Laboratory
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Materials Science Division Coal Technology Quarterly Report: January-March 1976

Description: Quarterly report of the Argonne National Laboratory Materials Science Division regarding the evaluation of ceramic refractories to withstand abrasion-corrosion by coal slag that will be encountered in the Bituminous Coal Research (BCR) Bi-Gas coal-gasification pilot plant, development of computer models to predict corrosion and erosion behavior of materials, and analysis of pilot-plant components that have failed or are removed from service for other reasons.
Date: 1976?
Creator: Argonne National Laboratory
open access

Physics of Reactor Safety, Quarterly Report: April-June 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 RSR safety analysis 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 DEMO safety-related critical experiments by members of the Zero Power Reactor (ZPP) Planning and Exper… more
Date: 1976?
Creator: Argonne National Laboratory. Applied Physics Division.
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Physics of Reactor Safety, Quarterly Report: July-September 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 RSR safety analysis program, analysis of critical assembly experiments, and work on reactor core thermal-hydraulic.
Date: December 1976
Creator: Argonne National Laboratory. Applied Physics Division.
open access

Radiological and Environmental Research Division Annual Report: Part 2, Center for Human Radiobiology, July 1975-June 1976

Description: Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to the Center for Human Radiobiology. The papers in this report deal with several different aspects of the Center's studies of the effects of internally deposited radionuclides in humans: experimental and theoretical research on the induction of tumors by alphaparticle irradiation (papers 1-4); medical effects (papers 5-8); metabolism and dosimetry (papers 9-17); metho… more
Date: 1976?
Creator: Argonne National Laboratory. Radiological and Environmental Research Division.
open access

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.
open access

Automated Approach to Quantitative Error Analysis in Neutron Transport Calculations

Description: A method is described how a quantitative measure for the robustness of a given transport theory code for coarse network calculations can be obtained. A code, that performs this task automatically and at only nominal cost, is described and has been implemented for slab geometry. This code generates also user oriented benchmark problems which exhibit the analytic behavior at interfaces.
Date: September 1976
Creator: Bareiss, Erwin H. & Derstine, Keith L.
open access

Three-Dimensional Thermal-Neutron Radiography

Description: Three-dimensional radiographic methods provide a means of determining the depth of defect indications and minimizing the confusion that results from overlapping images of structures at various depths in an object. One method of obtaining and displaying three-dimensional radiographic images is multiple-film laminagraphy, i.e., a series of radiographic films taken at different orientations can be viewed superimposed to present a sharply focused image of any desired object plane. Methods that use … more
Date: October 1976
Creator: Berger, H. & Reimann, K. J.
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Experimental Study of the Neutronics of the First Gas Cooled Fast Reactor Benchmark Assembly (GCFR Phase 1 Assembly)

Description: The Gas Cooled Fast Reactor (GCFR) Phase I Assembly is the first in a series of ZPR-9 critical assemblies designed to provide a reference set of reactor physics measurements in support of the 300 MW(e) GCFR Demonstration Plant designed by General Atomic Company. The Phase I Assembly was the first complete mockup of a GCFR core ever built. A set of basic reactor physics measurements were performed in the assembly to characterize the neutronics of the assembly and assess the impact of the neutron… more
Date: December 1976
Creator: Bhattacharyya, S. K.
open access

Germanium-Lithium Argon Scanning System (GLASS) : Design and Experience Through 1974

Description: The germanium-lithium argon scanning system (GLASS) was installed in EBR-II to monitor and analyze the gamma activity of the reactor cover gas and the reactor building air. GLASS has the capability to identify and measure 20 or more gamma peaks. Applied to the reactor cover gas, this capability has proven useful in identifying the source of fission-gas leakage from fuel elements. The gamma-peak data can clearly distinguish a carbide-fuel source from an oxide-fuel source and can often help disti… more
Date: July 1976
Creator: Brunson, G. S.
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Uses of Advanced Pulsed Neutron Sources. Report of a Workshop Held at Argonne National Laboratory, October 21-24, 1975

Description: This report contains the conclusions that were drawn by nine panels of scientists in the fields of Biology; Chemical Spectroscopy; Chemical Structures of Crystalline Solids; Chemical Structures of Disordered Solids and Inhomogeneous Systems; Dynamics of Solids, Liquids, Glasses, and Gases; Magnetism; Neutron Sources; and Radiation Effects. The nine panel reports describe the applications found in these scientific areas, accompanying them with conceptual instruments designed for the measurements… more
Date: 1976?
Creator: Carpenter, J. M. & Werner, S. A.
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