Resource Type
Serial/Series Title
GJBX
336
Atomic Energy Commission Reports
283
United States Department of Energy Grand Junction Office Reports
113
U.S. Waterways Experiment Station Reports
100
Argonne National Laboratory Reports
94
Technical report (U.S. Army Engineer Waterways Experiment Station)
90
United States Geological Survey Reports
63
Water Resources Investigations Reports
60
Habitat Development Field Investigations
58
Aerial Radiometric and Magnetic Reconnaissance Survey of Portions of the Great Plains and Central Lowlands
43
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PTOLEMY : a Program for Heavy-Ion Direction-Reaction Calculations
Many important additions and improvements have been made to Ptolemy since the previously-documented version of February 1976. An indication of this is that the list of keywords has been expanded by thirty. Collective-model inelastic excitement has been added. The computation of the transfer DWBA amplitudes has been significantly improved by the use of interpolation in the Ri +Ro variable. Elastic scattering and reactions involving identical particles may now be computed. Simultaneous optical model fits to several different elastic channels are possible. Significant changes to this manual are marked with a vertical bar in the left margin and should be carefully reviewed. In addition the contents of the manual have been extensively re-ordered.
Date:
1978
Creator:
Macfarlane, M. H. & Pieper, Steven C.
Object Type:
Report
System:
The UNT Digital Library
Advanced Fuel Cell Development Progress Report: October-December 1977
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.
Object Type:
Report
System:
The UNT Digital Library
Comparison of REXCO Code Predictions with SRI SM-2 Experimental Results
This report deals with the REXCO-code predictions of the SRI SM-2 test. Two calculations were performed with the REXCO-HEP code: one used the pressure history of the core detonation products as input and the other the pressure-volume relations of the detonation products as input. The other inputs of the computer analysis are the vessel and the core-barrel dimensions and boundary conditions, the constitutive equations of the vessel and the core barrel materials, and the equation of state for the coolant. The REXCO-predicted well deformations, pressure loadings, and dynamic strain histories at various gauge positions are compared with the experimental data. Results of the comparisons are discussed.
Date:
August 1978
Creator:
Chang, Y. W. & Gvildys, J.
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
Development of Lithium/Metal Sulfide Batteries at Argonne National Laboratory: Summary Report for 1977
This report consists of highlights for 1977 of Argonne National Laboratory's program on the development of lithium/metal sulfide batteries.
Date:
March 1978
Creator:
Nelson, P. A.; Steunenberg, R. K.; Chilenskas, A. A.; Gay, E. C.; Battles, J. E.; Hornstra, F. et al.
Object Type:
Report
System:
The UNT Digital Library
High-Performance Batteries for Stationary Energy Storage and Electric-Vehicle Propulsion, Progress Report: October-December 1977
Quarterly progress report discussing projects by Argonne National Laboratories and subcontractors related to high-temperature batteries.
Date:
March 1978
Creator:
Nelson, P. A.; Steunenberg, R. K.; Chilenskas, A. A.; Gay, E. C.; Battles, J. E.; Hornstra, F. et al.
Object Type:
Report
System:
The UNT Digital Library
Physics of Reactor Safety, Quarterly Report: October-December 1977
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 thermal-hydraulic code development performed in the Components Technology Division is also included in this report.
Date:
March 1978
Creator:
Argonne National Laboratory. Applied Physics Division.
Object Type:
Report
System:
The UNT Digital Library
DISPL: a Software Package for One and Two Spatially Dimensioned Kinetics-Diffusion Problems
DISPL is a software package for solving some second-order nonlinear systems of partial differential equations including parabolic, elliptic, hyperbolic, and some mixed types such as parabolic-elliptic equations. Fairly general nonlinear boundary conditions are allowed as well as interface conditions for problems in an inhomogeneous media. The spatial domain is one- or two-dimensional with Cartesian, cylindrical, or spherical (in one dimension only) geometry. The numerical method is based on the use of Galerkin's procedure combined with the use of B-splines in order to reduce the system of PDE's to a system of ODE's. The latter system is then solved with a sophisticated ODE software package. Software features include extensive dump/restart facilities, free format input, moderate printed output capability, dynamic storage allocation, and three graphics packages.
Date:
November 1978
Creator:
Leaf, G. K.; Minkoff, M.; Byrne, G. D.; Sorensen, D.; Bleakney, T. & Saltzman, J.
Object Type:
Report
System:
The UNT Digital Library
Proceedings of the 1978 Symposium on Instrumentation and Control for Fossil Demonstration Plants : June 19-21, 1978, Newport Beach Marriott, Newport Beach, California
This conference covers various aspects of fossil-fuel power plants based on coal or coal-conversion products, as well as the process control equipment involved in the conversion or combustion processes.
Date:
June 1978
Creator:
Argonne National Laboratory
Object Type:
Report
System:
The UNT Digital Library
Domain and Surface Structures of Sodium Tungsten Bronzes, NaxWO₃ (0.4 [x [1)
The domain and surface structures of metallic sodium tungsten bronzes, NaxWO₃, 0.4 < x < 1, were studied using optical microscopy, supplemented by chemical methods, photoelectron spectroscopy, electron microscopy, etc. The birefringent, multidomain structure of the bronze is exhibited by a sodium-deficient, epitaxial surface film and hence is not, as reported elsewhere, a bulk property. The film can be synthesized by anodic electrolysis in alkaline solution and can exist only epitaxially with the substrate. It is chemically inert, translucent, and often laminated to a multilayered film. The film domain is hypersensitive to lateral stress and to thermal change, and appears to be modulated by minute structural changes of the substrate. This epitaxial modulation of the film is strikingly large at the phase transitions of the substrate induced by slightly different tiltings of the oxygen octahedra. The domain-wall movement is often slow enough to be visible, and that by thermal effect is occasionally accompanied by an audible, high-pitched, snapping sound.
Date:
September 1978
Creator:
Atoji, Masao
Object Type:
Report
System:
The UNT Digital Library
Tritium and Hydrogen Transport in LMFBR Systems: EBR-II, CRBR, and FFTF
A tritium and hydrogen transport model has been employed to simulate concentration profiles, tritium losses to auxiliary containment systems, and cold trap burdens for EBR-II, CRBR, and FFTF. Experimental data from EBR-II were found to correlate well with calculated tritium and hydrogen profiles. A major change relative to previous transport models, namely, the inhibiting effect of oxide coatings on tritium permeation through reactor structural surfaces, has been incorporated into the current model. Tritium release rates to auxiliary systems where oxide barrier effects were included were predicted to be approximately two orders of magnitude lower than those for the reference case where structural surfaces were assumed to be totally oxide-free. Tritium releases during operation of large LMFBRs are expected to present essentially no hazard to the environment.
Date:
September 1978
Creator:
Renner, T. A. & McPheeters, C. C.
Object Type:
Report
System:
The UNT Digital Library
Radiological and Environmental Research Division Annual Report: Part 2, Center for Human Radiobiology, July 1977-June 1978
Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to the Center for Human Radiobiology.
Date:
June 1978
Creator:
Rowland, R. E.
Object Type:
Report
System:
The UNT Digital Library
Proceedings of the Workshop on Hydrocarbon Processing Mixing and Scale-Up Problems
A workshop was convened by the Division of Fossil Fuel Utilization of the US Department of Energy in cooperation with the Particulate and Multiphase Process Program of the National Science Foundation to identify needs for fundamental engineering support for the design of chemical reactors for processing heavy hydrocarbon liquids. The problems associated with dispersing liquid hydrocarbons in a reacting gas and mixing within the gas phase are of primary concern. The transactions of the workshop begin with an introduction to the immediate goals of the Department of Energy. Fuel cell systems and current research and development are reviewed. Modeling of combustion and the problems of soot formation and deposits in hydrocarbon fuels are next considered. The fluid mechanics of turbulent mixing and its effect on chemical reactions are then presented. Current experimental work and process development provide an update on the present state-of-the-art.
Date:
December 1978
Creator:
Gabor, J. D.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Ceramic Refractories for Slagging Gasifiers : Summary of Progress to Date
Commercial refractories were tested for up to 500 h in both basic and acidic slags. The slag compositions typify those expected in slagging coal gasifiers. The slag temperatures ranged up to 1600 degrees C. Compositions tested have included silicon carbides, chrome-alumina-magnesia spinels, and alumina and magnesia-based refractories with various amounts of chromia and silica. In some tests, the cold faces were water cooled. With water cooling, the silicon carbides showed virtually no attack after 500 h. In the absence of water cooling, the chrome-alumina-magnesia spinels were the most resistant to slag attack but were subject to thermal-shock cracking. Alumina-chrome refractories performed well in acid slags when water cooled, are probably more stable than silicon carbide in coal-gasification atmospheres, and, in the form of ramming mixes, showed excellent thermal-shock resistances. Plans for future testing are described.
Date:
September 1978
Creator:
Kennedy, C. R.; Swaroop, R.; Jones, D. J.; Fousek, R. J.; Poeppel, R. B. & Stahl, D.
Object Type:
Report
System:
The UNT Digital Library
Investigations of Materials Compatibility Relevant to the EBR-II system : FY 1977 and the Transition Period
Report on yearly investigations of components of the EBR-II reactor plant and on out-of-reactor experiments in which materials or techniques are tested before they are used in the EBR-II reactor system.
Date:
February 1978
Creator:
Longua, K. J.; Ruther, W. E.; Shields, J. A. & Clark, A. F.
Object Type:
Report
System:
The UNT Digital Library
Approximations of Gamma Cross Sections for Fast Nuclear Reactors
The report shows a method to approximate a P₁ scattering solution for the flux in a fast reactor, using an isotropic, but not a diagonal-transport-approximation scattering matrix. Presented are flux errors relative to a P₁ solution for different levels of transport approximation in an EBR-II type of core surrounded by a stainless steel reflector. Problems associated with the use of the method are also presented.
Date:
1978?
Creator:
Grimm, K. N. & Meneghetti, D.
Object Type:
Report
System:
The UNT Digital Library
Preliminary Evaluation of Several Nondestructive-Evaluation Techniques for Silicon Nitride Gas-Turbine Rotors
Several nondestructive-evaluation (NDE) techniques have been examined to establish their effectiveness for detecting critically sized flaws in silicon nitride gas-turbine rotors. Preliminary results have been obtained for holographic interferometry, acoustic microscopy, dye-enhanced radiography, acoustic emission, and acoustic-impact testing techniques. This report discusses the relative effectiveness of these techniques in terms of their applicability to the rotor geometry and ability to detect critically sized flaws. Where feasible, flaw indications were verified by alternative NDE techniques or destructive examination. This study has indicated that, since the various techniques have different advantages, ultimately a reliable interrogation of ceramic rotors may require the application of several NDE methods.
Date:
1978?
Creator:
Kupperman, D. S.; Sciammarella, C.; Lapinski, N. P.; Sather, A.; Yuhas, D.; Kessler, L. et al.
Object Type:
Report
System:
The UNT Digital Library
Coupled Hydrodynamic-Structural Response Analysis of Piping Systems
This report describes in detail the expansion of the ICEPEL code for the coupled hydrodynamic-structural response analysis of pipe-elbow loops to general piping systems. A generalized piping-component model, a branching tce junction, and a surge-tank model are introduced and coupled with the pipe-elbow loop model so that a general piping system under the effect of internally traveling pressure pulses can be analyzed hydrodynamically, as well as structurally.
Date:
1978?
Creator:
A-Moneim, M. T.
Object Type:
Report
System:
The UNT Digital Library
Light-Water-Reactor Safety Research Program Quarterly Progress Report: July-September 1977
Quarterly report summarizing research and development on water-reactor-safety heat-transfer and flow problems, including: Loss-of-coolant accident research, transient fuel response and fission-product release, mechanical properties of zircaloy containing oxygen, and steam-explosion studies.
Date:
January 1978
Creator:
Argonne National Laboratory
Object Type:
Report
System:
The UNT Digital Library
PTAC: a Computer Program for Pressure-Transient Analysis, Including the Effects of Cavitation
PTAC was developed to predict pressure transients in nuclear-power-plant piping systems in which the possibility of cavitation must be considered. The program performs linear or nonlinear fluid-hammer calculations, using a fixed-grid method-of-characteristics solution procedure. In addition to pipe friction and elasticity, the program can treat a variety of flow components, pipe junctions, and boundary conditions, including arbitrary pressure sources and a sodium/water reaction. Essential features of transient cavitation are modeled by a modified column-separation technique. Comparisons of calculated results with available experimental data, for a simple piping arrangement, show good agreement and provide validation of the computational cavitation model. Calculations for a variety of piping networks, containing either liquid sodium or water, demonstrate the versatility of PTAC and clearly show that neglecting cavitation leads to erroneous predictions of pressure-time histories.
Date:
September 1978
Creator:
Kot, C. A. & Youngdahl, C. K.
Object Type:
Report
System:
The UNT Digital Library
Materials Technology for Coal-Conversion Processes Progress Report: July-December 1977
Progress report on the activities of the Argonne National Laboratory Materials Science Division regarding studies done on refractory concretes and metallic materials being used or intended for use in coal-conversion processes, erosive wear, nondestructive testing, corrosion, chemical degradation, and failure analysis.
Date:
1978?
Creator:
Argonne National Laboratory. Materials Science Division.
Object Type:
Report
System:
The UNT Digital Library
Studies of Nuclear Waste Migration in Geologic Media, Annual Report: November 1976-October 1977
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.
Object Type:
Report
System:
The UNT Digital Library
EBR-II Environmental Instrumented Subassembly XX08 : Engineering and Assembly
Subassembly XX08 is a fueled and instrumented subassembly designed primarily for an ongoing program to investigate the thermal-hydraulic core environment within EBR-II under normal and off-normal plant operating conditions. XX08 contains 58-xenon-tagged, EBR-II Mark-II driver-fuel elements. The Mark-II fuel is expected to provide XX08 with an irradiation lifetime three times as great as that attained with its predecessor, XX07, i.e., a 9 versus 2.9% burnup. A burnup of 9 at.% is equivalent to about 29,000 MWt dyays of EBR-II reactor operation, which corresponds to 11 reactor runs at 2700 MWd per run.
Date:
May 1978
Creator:
Smaardyk, A.; Filewicz, E. C.; Longnecker, A. A.; Poloncsik, J.; Tokar, J. V.; Walker, D. E. et al.
Object Type:
Report
System:
The UNT Digital Library
Fuel Cycle Program Progress Report: January-September 1977
Report of the Argonne National Laboratory Chemical Engineering Division on fuel-cycle studies including pyro-chemical separation of plutonium and americium oxides from contaminated materials of construction such as steel, advanced solvent extraction techniques in the development of centrifugal contactors for use in Purex processes, and a review and evaluation of the encapsulation of high-level waste in a metal matrix.
Date:
1978?
Creator:
Steindler, M. J.; Ader, M.; Bernstein, G.; Flynn, K. F.; Gerding, T. J.; Jardine, L. J. et al.
Object Type:
Report
System:
The UNT Digital Library