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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 equations, the use of the code, and the implementation on the IBM 370/195 and CDC 7600 of the version of SYN3D available through the Argonne Code Center.
Date: 1976
Creator: Adams, C. H.

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 scheme has been developed to solve non-linear boundary-value problems. This suppression scheme has been used in conjunction with a Newton-Raphson method to improve a stable convergence process at the yield surface in elastic-plastic problems. Results presented indicate the accuracy of this numerical scheme. It appears to be possible to extend this method for more complicated situations.
Date: December 1976
Creator: Ahmed, Habib Uddin

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 step toward better understanding of the pool-type system and of the advantages and disadvantages of the various possible approaches to its design.
Date: May 1976
Creator: Amorosi, A.; Hutter, E.; Marciniak, T. J.; Monson, H. O.; Seidensticker, R. W. & Simmons, W. R.

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 breakdown of the gas layer, during which the two liquids locally fragment, intermix, and pressurize very rapidly. The experimental results were compared with various mechanistic models that had been proposed to explain vapor explosions. Early models seemed inconsistent with the results. More recent theories suggest that vapor explosions may be caused by a nucleation limit or by dynamic mixing combined with high surface-heat-transfer rates. Both types of models are consistent with the results.
Date: April 1976
Creator: Anderson, R. P. & Bova, L.

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 emit air pollutants, the cost of not complying with some regulations is significantly less than the cost of compliance. This final report on the Phase 1 research presents highlights of what has been learned, the mechanisms developed for transferring results to users, a bibliography of documents produced during the project, and a collection of correspondence, articles, and evaluation illuminating the use of project work by others.
Date: October 1976
Creator: Argonne National Laboratory

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

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

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

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 components that have failed or are removed from service.
Date: 1976?
Creator: Argonne National Laboratory

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

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 Experiments Group.
Date: 1976?
Creator: Argonne National Laboratory. Applied Physics Division.

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); methods for the detr-mination of radioactivity (papers 18-25); and processing of data (papers 26-27).
Date: 1976?
Creator: Argonne National Laboratory. Radiological and Environmental Research Division.

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 (due in part to very conservative data analysis and an inefficient geometry), the results did demonstrate that there is no intrinsic reason why reactor materials cannot produce a vapor explosion.
Date: March 1976
Creator: Armstrong, D. R.; Goldfuss, G. T. & Gebner, R. H.

What About Metric?

Description: Pamphlet issued by the United States National Bureau of Standards discussing the reasons that the U.S. decided passed the Metric Conversion Act of 1975 and provides tables, illustrations, and formulas for converting between customary units and metric units of measuring weight, length, volume, and temperature. It also includes a discussion of how one might expect to use metric measurements in the marketplace, in the home, and at work.
Date: October 1976
Creator: Barbrow, Louis E. & Halpin, Suellen

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.

Automatic Measurement of Network Parameters: A Survey

Description: Report issued by the Bureau of Standards over a survey conducted on measurement methods of network parameters. As stated in the introduction, "this paper is concerned with the development of automatic methods of measuring basically the magnitudes and phase differences, or the complex ratio of two sinusoidal voltages, and applications of this capability to determining complex reflection coefficients and transmission coefficients and group delay times of electrical networks" (p. 1). This report includes tables, and illustrations.
Date: June 1976
Creator: Beatty, Robert William

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 multiple-film laminagraphy for three-dimensional thermal-neutron images will be described.
Date: October 1976
Creator: Berger, H. & Reimann, K. I.

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 streaming on the various integral parameters. The analysis of the experiments was carried out using ENDF/B-IV based data and two-dimensional diffusion theory methods. The Benoist method of using directional diffusion coefficients was used to treat the anisotropic effects of neutron streaming within the framework of diffusion theory. Calculated predictions of most integral parameters in the GCFR showed the same kinds of agreements with experiment as in earlier LMFBR assemblies.
Date: December 1976
Creator: Bhattacharyya, S. K.