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COMMIX-1AR/P. a Three-Dimensional Transient Single-Phase Computer Program for Thermal Hydraulic Analysis of Single and Multicomponent Systems

Description: The COMMIX-1AR/P computer code is designed for analyzing the steady-state and transient aspects of single-phase fluid flow and heat transfer in three spatial dimensions. This version is an extension of the modeling in COMMIX-1A to include multiple fluids in physically separate regions of the computational domain, modeling descriptions for pumps, radiation heat transfer between surfaces of the solids which are embedded in or surround the fluid, a k-{var epsilon} model for fluid turbulence, and improved numerical techniques. The porous-medium formulation in COMMIX allows the code to be applied to a wide range of problems involving both simple and complex geometrical arrangements. The basic equations, underlying assumptions, and solution techniques are presented for the entire computer code, covering both old and new features.
Date: July 1991
Creator: Blomquist, R. A.; Garner, P. L. & Gelbard, Ely M.

COMMIX-1AR/P. a Three-Dimensional Transient Single-Phase Computer Program for Thermal Hydraulic Analysis of Single and Multicomponent Systems, Volume 2: User's Guide

Description: The COMMIX-1AR/P computer code is designed for analyzing the steady-state and transient aspects of single-phase fluid flow and heat transfer in three spatial dimensions. This version is an extension of the modeling in COMMIX-1A to include multiple fluids in physically separate regions of the computational domain, modeling descriptions for pumps, radiation heat transfer between surfaces of the solids which are embedded in or surround the fluid, a k-(epsilon) model for fluid turbulence, and improved numerical techniques. The porous-medium formulation in COMMIX allows the code to be applied to a wide range of problems involving both simple and complex geometrical arrangements. The input preparation and execution procedures are presented for the COMMIX-1AR/P program and several post processor programs which produce graphical displays of the calculated results. This document provides a step-by-step of how to use the program, including an input guide and a sample problem.
Date: September 1992
Creator: Garner, P. L.; Blomquist, R. N. & Gelbard, Ely M.

COMMIX-1AR/P. a Three-Dimensional Transient Single-Phase Computer Program for Thermal Hydraulic Analysis of Single and Multicomponent Systems, Volume 3: Programmer's Guide

Description: The COMMIX-LAR/P computer program is designed for analyzing the steady-state and transient aspects of single-phase fluid flow and heat transfer in three spatial dimensions. This version is an extension of the modeling in COMMIX-lA to include multiple fluids in physically separate regions of the computational domain, modeling descriptions for pumps, radiation heat transfer between surfaces of the solids which are embedded in or surround the fluid, a keg model for fluid turbulence, and improved numerical techniques. The porous-medium formulation in COMMIX allows the program to be applied to a wide range of problems involving both simple and complex geometrical arrangements. The internal aspects of the COMMIX-LAR/P program are presented, covering descriptions of subprograms, variables, and files. This document provides a description of each subroutine and variable, showing linkage among these and their relation to the equations and variables presented in Volume 1.
Date: September 1992
Creator: Garner, P. L.; Blomquist, R. N. & Gelbard, Ely M.

COMMIX-PPC. a Three-Dimensional Transient Multicomponent Computer Program for Analyzing Performance of Power Plant Condensers

Description: The COMMIX-PPC computer program is an extended and improved version of earlier COMMIX codes and is specifically designed for evaluating the thermal performance of power plant condensers. The COMMIX codes are general-purpose computer programs for the analysis of fluid flow and heat transfer in complex industrial systems. In COMMIX-PPC, two major features have been added to previously published COMMIX codes. One feature is the incorporation of one-dimensional conservation of mass, momentum, and energy equations on the tube side, and the proper accounting for the thermal interaction between shell and tube side through the porous medium approach. The other added feature is the extension of the three-dimensional conservation equations for shell-side flow to treat the flow of a multicomponent medium. COMMIX-PPC is designed to perform steady-state and transient three-dimensional analysis of fluid flow with heat transfer in a power plant condenser. However, the code is designed in a generalized fashion so that, with some modification, it can be used to analyze processes in any heat exchanger or other single-phase engineering applications.
Date: August 1991
Creator: Chien, T. H.; Domanus, H. M. & Sha, William T.

COMMIX-PPC: A Three-Dimensional Transient Multicomponent Computer Program for Analyzing Performance of Power Plant Condensers, Volume 1: Equations and Numerics

Description: Report on the COMMIX-PPC computer program, designed to evaluate the thermal performance of power plant condensers. This first volume "describes in detail the basic equations, formulation, solution procedures, and models for auxiliary phenomena" (p. iv).
Date: February 1993
Creator: Chien, T. H.; Domanus, H. M. & Sha, William T.

A Comparative Study of Iron-, Nickel-, and Cobalt-Base Weldments Exposed in TVA 20-MW and Rocketdyne Atmospheric Fluidized Bed Combustors

Description: Experimental iron-, nickel-, and cobalt-base weldment materials were exposed in TVA 20-MW and Rocketdyne atmospheric fluidized bed combustors (AFBCs) at 849 degrees C for 1261 h and 871 degrees C for 1000 h, respectively. Post-exposure analyses were conducted at Argonne National Laboratory. All specimens experienced different degrees of internal oxidation/sulfidation. Among eight filler materials, Marathon 25/35R and Haynes 188 showed the least corrosion attack, i.e., less than 0.5 mm/yr. A high nickel content in the weldment was unfavorable for corrosion resistance in the AFBC environment. Differences in the coal/bed chemistry of the TVA and Rocketdyne systems yielded different corrosion behavior in the materials. Calcium sulfate deposits on the specimens significantly affected the internal oxidation/sulfidation of the alloys. The results of this study supplement the material data base, in particular that of weldment performance, and aid in materials selection for AFBC applications.
Date: June 1990
Creator: Wang, D. Y. & Natesan, K.

Comparison of Cast-in-Place Concrete Versus Precast Concrete Stay-in-Place Forming Systems for Lock Wall Rehabilitation

Description: "The objectives of this report are as follows: (a) To present the design and details utilized on the precast concrete panel rehabilitation at Troy Lock. (b) To compare the results of precast concrete panel rehabilitation with previous cast-in-place repairs, with respect to quality, cost, and schedule. (c) To recommend refinements in the details and methods of fabrication and erection of the precast panels, based on lessons learned from work performed at Troy Lock." (p. 2).
Date: October 1993
Creator: Miles, William R.

Complete Bouguer and Isostatic Residual Gravity Maps of the Anadarko Basin, Wichita Mountains, and Surrounding Areas, Oklahoma, Kansas, Texas, and Colorado

Description: From abstract: This report contains the complete Bouger and isostatic residual gravity maps of the Anadarko basin, Wichita Mountains, and surrounding areas on parts of Oklahoma, Kansas, Texas and Colorado that were compiled using gravity data from 11,023 stations.
Date: 1992
Creator: Robbins, Stephen L. & Keller, G. Randy, Jr.

Correlation of the West Canyon, Lake Point, and Bannock Peak Limestones (Upper Mississippian to Middle Pennsylvanian), Basal Formations of the Oquirrh Group, Northern Utah and Southeastern Idaho

Description: The following report presents detailed lethologic and conodont biostratigraphic data from four measured sections in the lower part of the Oquirrh Group in the Oquirrh Mountains of Utah and the Deep Creek and Samaria Mountains of Idaho.
Date: 1994
Creator: Davis, L. E.; Dyman, T. S. & Webster, G. D.

Critical Review of Glass Performance Modeling

Description: Borosilicate glass is to be used for permanent disposal of high-level nuclear waste in a geologic repository. Mechanistic chemical models are used to predict the rate at which radionuclides will be released from the glass under repository conditions. The most successful and useful of these models link reaction path geochemical modeling programs with a glass dissolution rate law that is consistent with transition state theory. These models have been used to simulate several types of short-term laboratory tests of glass dissolution and to predict the long-term performance of the glass in a repository. Although mechanistically based, the current models are limited by a lack of unambiguous experimental support for some of their assumptions. The most severe problem of this type is the lack of an existing validated mechanism that controls long-term glass dissolution rates. Current models can be improved by performing carefully designed experiments and using the experimental results to validate the rate-controlling mechanisms implicit in the models. These models should be supported with long-term experiments to be used for model validation. The mechanistic basis of the models should be explored by using modern molecular simulations such as molecular orbital and molecular dynamics to investigate both the glass structure and its dissolution process.
Date: July 1994
Creator: Bourcier, William L.

The DART Dispersion Analysis Research Tool: a Mechanistic Model for Predicting Fission-Product-Induced Swelling of Aluminum Dispersion Fuels : User's Guide for Mainframe, Workstation, and Personal Computer

Description: This report describes the primary physical models that form the basis of the DART mechanistic computer model for calculating fission-product-induced swelling of aluminum dispersion fuels; the calculated results are compared with test data. In addition, DART calculates irradiation-induced changes in the thermal conductivity of the dispersion fuel, as well as fuel restructuring due to aluminum fuel reaction, amorphization, and recrystallization. Input instructions for execution on mainframe, workstation, and personal computers are provided, as is a description of DART output. The theory of fission gas behavior and its effect on fuel swelling is discussed. The behavior of these fission products in both crystalline and amorphous fuel and in the presence of irradiation-induced recrystallization and crystalline-to-amorphous-phase change phenomena is presented, as are models for these irradiation-induced processes.
Date: August 1995
Creator: Rest, J.

Data Dictionary and Discussion for the Midnite Mine GIS Database

Description: Abstract: A geographic information system (GIS) database has been developed by the U.S. Bureau of Mines (USBM) for the Midnite Mine and surroundings in northeastern Washington State (Stevens County) on the Spokane Indian Reservation. The mine is an open pit uranium mine which has been inactive since 1981. The GIS database was compiled to serve as a repository and source of historical and research information on the mine site. The database supported USBM hydrological and reclamation research on the mine site. The database also will be used by the Bureau of Land Management and the Bureau of Indian Affairs (as well as others) for environmental assessment and reclamation planning for future remediation and reclamation of the site. This report describes the data in the GIS database and their characteristics. The report also discusses known backgrounds on the data sets and any special considerations encountered by the USBM in developing the database. Most of the database also is planned to be available to the public as a two-CD-ROM set, although separately from this report.
Date: 1996
Creator: Peters, Douglas C.; Smith, M. Antoinette & Ferderer, David A.

Design and Development of Bendway Weirs for the Dogtooth Bend Reach, Mississippi River: Hydraulic Model Investigation

Description: From introduction: This report presents the results of a movable-bed model investigation concerned with the development of plans for the improvement of the Dogtooth Bend reach of the Mississippi River.
Date: August 1994
Creator: Derrick, David L.; Pokrefke, Thomas J., Jr.; Boyd, Marden B.; Crutchfield, James P. & Henderson, Raymond R.

Design-Development and Operation of the Experimental Boiling-Water Reactor (EBWR) Facility, 1955--1967

Description: The Experimental Boiling-Water Reactor (EBWR) was designed, built, and operated to provide experience and engineering data that would demonstrate the feasibility of the direct-cycle, boiling-water reactor and be applicable to improved, larger nuclear power stations; and was based on information obtained in the first test boiling-water reactors, the BORAX series. EBWR initially produced 20 MW(t), 5 MW(e); later modified and upgraded, as described and illustrated, it was operated at up to 100 MW(t). The facility fulfilled its primary mission - demonstrating the practicality of the direct-boiling concept - and, in fact, was the prototype of some of the first commercial plants and of reactor programs in some other countries. After successful completion of the Water-Cooled Reactor Program, EBWR was utilized in the joint Argonne-Hanford Plutonium Recycle Program to develop data for the utilization of plutonium as a fuel in light-water thermal systems. Final shutdown of the EBWR facility followed the termination of the latter program.
Date: November 1990
Creator: Boing, L. E.; Wimunc, E. A. & Whittington, G. A.

Detection and Control of Spontaneous Heating in Coal Mine Pillars--a Case Study

Description: This U.S. Bureau of Mines study examined spontaneous heating episodes in coal mine pillars in an active underground coal mine. The information obtained from these incidents was then analyzed to learn which sampling methods provided the earliest indication of pillar heating. The objective of this study was to discover if the location of future events of pillar spontaneous heating could be inferred from the available information. The spontaneous heating-prone area in this evaluation involved pillars located just in by the mine portals. Several detection methods were used to determine gas levels outside as well as inside the affected pillars. It was hoped that, by incorporating external and internal sampling methods into an organized program, locations undergoing spontaneous heating could be determined more readily. This study found that by drilling small-diameter boreholes into the pillars, then obtaining gas samples from the affected pillars, the ability to locate early spontaneous heating episodes was improved. However, the ability to accurately predict future spontaneous heating events remains in question.
Date: 1995
Creator: Timko, Robert J. & Derick, R. Lincoln

Detection and Location of Leaks in District Heating Steam Systems: Survey and Review of Current Technology and Practices

Description: This report presents the results of a survey undertaken to identify and characterize current practices for detecting and locating leaks in district heating systems, particular steam systems. Currently used technology and practices are reviewed. In addition, the survey was used to gather information that may be important for the application of acoustic leak detection. A few examples of attempts to locate leaks in steam and hot water pipes by correlation of acoustic signals generated by the leaks are also discussed.
Date: March 1992
Creator: Kupperman, D. S.; Raptis, A. C. & Lanham, R. L.

Development of a Boron-Copper Neutron Absorber Composite

Description: This report describes the fabrication of a new boron-copper neutron absorbing material that was developed to meet the upgrading needs of the Intense Pulsed Neutron Source (IPNS) at Argonne National Laboratory. To increase the intensity of the neutron beams from the IPNS, the target uranium was changed from depleted uranium to uranium enriched to 77.5% U-235. To keep the multiplication factor, k(sub eff) (number of fissions in one generation/number of fissions in preceding generation) at a safe level, a new neutron absorber material was needed. The previous materials, boral and cadmium, could not meet the new requirements and a search of the literature showed that no currently available material was acceptable.
Date: May 1991
Creator: Wiencek, T. C.; Thresh, H. R. & Summers, J. R.

Development of Coal Combustion Sensitivity Tests for Smoke Detectors

Description: Standard smoldering and flaming combustion tests using small coal samples have been developed by the U.S. Bureau of Mines as a method to evaluate the response of a smoke detector. The tests are conducted using a standard smoke box designed and constructed according to Underwriters Laboratories. The tests provide a standard, easily reproducible smoke characteristic for smoldering and flaming coal combustion, based upon a comparison of the smoke optical density and the response of a standard ionization chamber to the smoke. With these standard tests, the range of threshold limits for the response of a smoke detector and the detector's reliability can be evaluated for nearly identical smoke visibility and smoke physical characteristics. The detector's threshold response limits and reliability need to be well defined prior to the instrument's use as part of a mine fire warning system for improved mine safety.
Date: 1995
Creator: Edwards, John C. & Morrow, Gerald S.