Serial/Series Title
NACA Research Memorandums
391
NACA Technical Notes
347
Atomic Energy Commission Reports
330
GJBX
187
United States Department of Energy Grand Junction Office Reports
173
United States Geological Survey Reports
139
NACA Technical Memorandums
108
Argonne National Laboratory Reports
100
NACA Technical Reports
97
NACA Wartime Reports
93
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Fuel Cycle Programs, Quarterly Progress Report: July-September 1981
Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.
Date:
May 1982
Creator:
Steindler, M. J.; Bates, J. K.; Bowers, D. L.; Brock, R. E.; Cannon, T. F.; Castelli, D. L. et al.
Object Type:
Report
System:
The UNT Digital Library
Fuel Cycle Programs, Quarterly Progress Report: October-December 1981
Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.
Date:
May 1982
Creator:
Steindler, M. J.; Bates, J. K.; Cannon, T. F.; Couture, R. A.; Deeken, P. G.; Fagan, J. E. et al.
Object Type:
Report
System:
The UNT Digital Library
A Review of Leakage-Flow-Induced Vibrations of Reactor Components
The primary-coolant flow paths of a reactor system are usually subject to close scrutiny in a design review to identify potential flow-induced vibration sources. However, secondary-flow paths through narrow gaps in component supports, which parallel the primary-flow path, occasionally are the excitation source for significant vibrations even though the secondary-flow rates are orders of magnitude smaller than the primary-flow rate. These so-called leakage flow problems are reviewed here to identify design features and excitation sources that should be avoided. Also, design rules of thumb are formulated that can be employed to guide a design, but quantitative prediction of component response is found to require scale-model testing.
Date:
May 1983
Creator:
Mulcahy, T. M.
Object Type:
Report
System:
The UNT Digital Library
Simulation and Optimization Study of a Solar-Seasonal-Storage District-Heating System: The Fox River Valley Case study
A central solar-heating plant with seasonal heat storage in a deep underground aquifer is designed by means of a solar-seasonal-storage-system simulation code based on the Solar Energy Research Institute (SERI) code for Solar Annual Storage Simulation (SASS). This Solar Seasonal Storage Plant is designed to supply close to 100% of the annual heating and domestic-hot-water (DHW) load of a hypothetical new community, the Fox River Valley Project, for a location in Madison, Wisconsin. Some analyses are also carried out for Boston, Massachusetts and Copenhagen, Denmark, as an indication of weather and insolation effects. Analyses are conducted for five different types of solar collectors, and for an alternate system utilizing seasonal storage in a large water tank. Predicted seasonal performance and system and storage costs are calculated. To provide some validation of the SASS results, a simulation of the solar system with seasonal storage in a large water tank is also carried out with a modified version of the Swedish Solar Seasonal Storage Code MINSUN.
Date:
May 1983
Creator:
Michaels, Allan I.; Sillman, Sanford; Baylin, Frank & Bankston, Charles A.
Object Type:
Report
System:
The UNT Digital Library
PROSA-2: A Probabilistic Response-Surface Analysis and Simulation Code
Response-surface techniques have been developed for obtaining probability distributions of the consequences of postulated nuclear reactor accidents. In these techniques, probability distributions are assigned to the system and model parameters of the accident analysis. A limited number of parameter values (called knot points) are selected and input to a deterministic accident-analysis code. The results of the deterministic analyses are used to generate analytical functions (called response surfaces) that approximate the accident consequences in terms of selected system and model parameters. The response-surface methodology of this report includes both systematical and random knot-point selection schemes, second- and third-degree response surfaces, functional transformations of both input parameters and consequence variables, smooth synthesis of region-wise response surfaces and the treatment of random conditions for conditional distributions. The computer code PROSA-2 developed for implementing these techniques is independent of the deterministic accident-analysis codes.
Date:
May 1981
Creator:
Vaurio, J. K. & Fletcher, J.
Object Type:
Report
System:
The UNT Digital Library
Comparison of Costs for Solidification of High-Level Radioactive Waste Solutions: Glass Monoliths vs Metal Matrices
A comparative economic analysis was made of four solidification processes for liquid high-level radioactive waste. Two processes produced borosilicate glass monoliths and two others produced metal matrix composites of lead and borosilicate glass beads and lead and super-calcine pellets. Within the uncertainties of the cost (1979 dollars) estimates, the cost of the four processes was about the same, with the major cost component being the cost of the primary building structure. Equipment costs and operating and maintenance costs formed only a small portion of the building structure costs for all processes.
Date:
May 1981
Creator:
Jardine, L. J.; Carlton, R. E. & Steindler, M. J.
Object Type:
Report
System:
The UNT Digital Library
Algorithms for Automated Diagnosis of Faults in Physical Plant
This report presents a diagnostic automation that can be used to investigate classes of systems without feedback loops. This report shows the input needed for the automation, the algorithm used, and the PROLOG program for the simulation.
Date:
May 1983
Creator:
Gabriel, John R.
Object Type:
Report
System:
The UNT Digital Library
A Review of Metal-Matrix Encapsulation of Solidified Radioactive High-Level Waste
A reference conceptual flowsheet based on existing or developing technology for encapsulation of stabilized calcine pellets is discussed. Conclusions and recommendations are presented.
Date:
May 1978
Creator:
Jardine, L. J. & Steindler, M. J.
Object Type:
Report
System:
The UNT Digital Library
ANL Technical Support Program for DOE Environmental Restoration and Waste Management Annual Report for October 1991 - September 1992
Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site.
Date:
May 1993
Creator:
Bates, John K.
Object Type:
Report
System:
The UNT Digital Library
Nuclear Waste Programs Semiannual Progress Report: April-September 1992
This document reports on the work done by the Nuclear Waste Programs of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period April-September 1992. In these programs, studies are underway on the performance of waste glass and spent fuel in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.
Date:
May 1994
Creator:
Bates, John K.; Bradley, C. R.; Buck, E. C.; Dietz, N. L.; Ebert, William L.; Emery, J. W. et al.
Object Type:
Report
System:
The UNT Digital Library
Surveillance of Site A and Plot M : Report for 1994
The results of the environmental surveillance program conducted at Site A/Plot M in the Palos Forest Preserve area for 1994 are presented. The surveillance program is the ongoing remedial action that resulted from the 1976-1978 radiological characterization of the site. That study determined that very low levels of hydrogen-3 (as tritiated water) had migrated from the burial ground and were present in two nearby hand-pumped picnic wells. The current program consists of sample collection and analysis of air, surface and subsurface water, and bottom sediment.
Date:
May 1995
Creator:
Golchert, N. W.
Object Type:
Report
System:
The UNT Digital Library
Reaction of Glass During Gamma Irradiation in a Saturated Tuff Environment
The reaction between tuffaceous groundwater and actinide-doped SRL 165 and PNL 76-68 type glasses in a gamma radiation field has been studied at 90 degrees C for periods up to 278 days. The primary effect of the radiation field was the acidification of the leachate through the production of nitrogen acids. Acidification of the leachate was limited by bicarbonate in the groundwater, for all exposures tested. Nonirradiated experiments were performed to represent the lowest limit of radiation exposure. Both irradiated and nonirradiated experiments were performed with and without a tuff monolith present in the reaction vessel. Neither irradiation nor the presence of tuff had a major effect on the extent of glass reaction as measured by the leachate concentrations of various glass species or analysis of the reacted glass surfaces. This report discusses the results of leaching experiments performed in a gamma radiation field and in the absence of a radiation field.
Date:
May 1990
Creator:
Ebert, William L.; Bates, John K. & Gerding, Thomas J.
Object Type:
Report
System:
The UNT Digital Library
Two-Phase Flow Patterns and Frictional Pressure Gradients in a Small, Horizontal, Rectangular Channel
Two-phase flow patterns and frictional pressure gradients in flow in small, rectangular channels are being studies as part of a larger research program addressing phase-change heat transfer of pure refrigerants and refrigerant mixtures in plate-fin heat exchangers. Small rectangular flow channels were selected as representative of plain fin geometries. The particular channel reported herein has dimensions of 19.05 {times} 3.18 mm. Adiabatic flows of air/water mixtures, with the flow channel horizontal and the channel exit at near-atmospheric conditions, were utilized in the experiments. Analysis and interpretation of the pressure data relative to observed flow pattern transitions led to an objective method for determining the plug/bubble-to-slug flow transition. This method, together with visual observations, supplemented with photographic data, was used to develop a flow pattern man. A comparison of existing flow pattern maps for circular pipes, capillary tubes, and larger rectangular channels led to the conclusion that, while qualitative agreement exists, these maps are not generally applicable on a quantitative basis to the subject small rectangular channel. Two state-of-the-art correlations for frictional pressure gradient were evaluated, with particular emphasis on the practically important ranges of total mass quality and mass flux, from the standpoint of plate-fin heat exchangers designed as evaporators. …
Date:
May 1990
Creator:
Wambsganss, M. W.; Jendrzejczyk, J. A.; France, D. M. & Obot, Nsima T.
Object Type:
Report
System:
The UNT Digital Library
Annual Technical Report
Highlights of the Chemical Technology Division's activities during 1990, including electrochemical technology and advanced batteries and fuel cells, technology for coal-fired magnetohydrodynamics and fluidized-bed combustion, methods for recovery of energy from municipal waste, and techniques for treatment of hazardous organic waste, the reaction of nuclear waste glass and spent fuel under conditions expected for a high-level waste repository.
Date:
May 1991
Creator:
Argonne National Laboratory. Chemical Technology Division.
Object Type:
Report
System:
The UNT Digital Library
Activities and Operations of Argonne's Advanced Computing Research Facility : February 1990 through April 1991
This report reviews the activities and operations of the Advanced Computing Research Facility (ACRF) from February 1990 through April 1991. The ACRF is operated by the Mathematics and Computer Science Division at Argonne National Laboratory. The facility's principal objective is to foster research in parallel computing. Toward this objective, the ACRF operates experimental advanced computers, supports investigations in parallel computing, and sponsors technology transfer efforts to industry and academia.
Date:
May 1991
Creator:
Pieper, Gail W.
Object Type:
Report
System:
The UNT Digital Library
Experimental Program for Development and Evaluation of Nondestructive Assay Techniques for Plutonium Holdup
An outline is presented for an experimental program to develop and evaluate nondestructive assay techniques applicable to holdup measurement in plutonium-containing fuel fabrication facilities. The current state-of-the-art in holdup measurements is reviewed. Various aspects of the fuel fabrication process and the fabrication facility are considered for their potential impact on holdup measurements. The measurement techniques considered are those using gamma-ray counting, neutron counting, and temperature measurement. The advantages and disadvantages of each technique are discussed. Potential difficulties in applying the techniques to holdup measurement are identified. Experiments are proposed to determine the effects of such problems as variation in sample thickness, in sample distribution, and in background radiation. These experiments are also directed toward identification of techniques most appropriate to various applications. Also proposed are experiments to quantify the uncertainties expected for each measurement.
Date:
May 1977
Creator:
Brumbach, S. B.
Object Type:
Report
System:
The UNT Digital Library
First Assessment of Computations of Turbulent Bubbly Flow and Particulate Flow with the COMMIX-M Program
The COMMIX-M computer code, which describes steady-state and transient single- and multi-component flows in engineering systems, has been implemented to simulate suspension flows in laminar regimes and turbulent and bubbly particulate flows. This report presents a synopsis of the present code's capabilities, with particular emphasis on the recent development of turbulence models, and explains in detail the modifications necessary to simulate particulate flows and bubbly flows. First results of computations of turbulent bubbly and particulate flows are then given and compared with results of computations reported in the literature and with preliminary experimental results obtained at the Kernforschungszentrum Karlsruhe (Germany).
Date:
May 1994
Creator:
Bottoni, M.; Chang, F. C. & Ding, J.
Object Type:
Report
System:
The UNT Digital Library
Argonne National Laboratory-East Site Environmental Report for Calendar Year 1991
This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1991. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples.
Date:
May 1992
Creator:
Golchert, N. W.; Duffy, T. L. & Moos, L. P.
Object Type:
Report
System:
The UNT Digital Library
Argonne National Laboratory-East Site Environmental Report for Calendar Year 1992
This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1992. To evaluate the effects of ANL operations .on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples.
Date:
May 1993
Creator:
Golchert, N. W. & Kolzow, R. G.
Object Type:
Report
System:
The UNT Digital Library
Argonne National Laboratory-East Site Environmental Report for Calendar Year 1993
This annual report on the ANL environmental protection program provides the DOE, environmental agencies, and the public with information on the levels of radioactive and chemical pollutants in the vicinity of ANL and on the amounts, if any, added to the environment by ANL operations. It also summarizes compliance of ANL operations with applicable environmental laws and regulations and highlights significant accomplishments and problems related to environmental protection. The report follows the guidelines given in DOE Order 5400.1.
Date:
May 1994
Creator:
Golchert, N. W. & Kolzow, R. G.
Object Type:
Report
System:
The UNT Digital Library
Argonne National Laboratory-East Site Environmental Report for Calendar Year 1994
This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1994. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed.
Date:
May 1995
Creator:
Golchert, N. W. & Kolzow, R. G.
Object Type:
Report
System:
The UNT Digital Library
A Parallel Genetic Algorithm for the Set Partitioning Problem
In this dissertation the author reports on his efforts to develop a parallel genetic algorithm and apply it to the solution of set partitioning problem -- a difficult combinatorial optimization problem used by many airlines as a mathematical model for flight crew scheduling. He developed a distributed steady-state genetic algorithm in conjunction with a specialized local search heuristic for solving the set partitioning problem. The genetic algorithm is based on an island model where multiple independent subpopulations each run a steady-state genetic algorithm on their subpopulation and occasionally fit strings migrate between the subpopulations. Tests on forty real-world set partitioning problems were carried out on up to 128 nodes of an IBM SP1 parallel computer. The authors found that performance, as measured by the quality of the solution found and the iteration on which it was found, improved as additional subpopulation found and the iteration on which it was found, improved as additional subpopulations were added to the computation. With larger numbers of subpopulations the genetic algorithm was regularly able to find the optimal solution to problems having up to a few thousand integer variables. In two cases, high-quality integer feasible solutions were found for problems with 36,699 and 43,749 …
Date:
May 1994
Creator:
Levine, David
Object Type:
Report
System:
The UNT Digital Library
Glassy Slags for Minimum Additive Waste Stabilization: Interim Progress Report, May 1993-February 1994
Interim report describing progress to develop glassy slag waste forms that support environmental restoration efforts.
Date:
May 1994
Creator:
Feng, X.; Wronkiewicz, David J.; Bates, J. K.; Brown, N. R.; Buck, E. C.; Dietz, N. L. et al.
Object Type:
Report
System:
The UNT Digital Library
Studies of Acute and Chronic Radiation Injury at the Biological and Medical Research Division, Argonne National Laboratory, 1953-1970 : Description of Individual Studies, Data Files, Codes, and Summaries of Significant Findings
Between 1953 and 1970, studies on the long-term effects of external x-ray and {gamma} irradiation on inbred and hybrid mouse stocks were carried out at the Biological and Medical Research Division, Argonne National Laboratory. The results of these studies, plus the mating, litter, and pre-experimental stock records, were routinely coded on IBM cards for statistical analysis and record maintenance.
Date:
May 1994
Creator:
Grahn, D.
Object Type:
Report
System:
The UNT Digital Library