Hydrogeochemical and Stream Sediment Reconnaissance Basic Data for Grand Island NTMS Quadrangle, Nebraska; Kansas: Appendix C

Data collected as part of a hydrogeochemical and stream sediment reconnaissance of Grand Island NTMS quadrangle in Kansas and Nebraska including laboratory data on well water and stream sediments as well as field data.
Date: July 31, 1980
Creator: National Uranium Resource Evaluation Program
Object Type: Dataset
System: The UNT Digital Library

Uranium in Granites From the Southwestern United States: Actinide Parent-Daughter Systems, Sites and Mobilization: First Year Report, [Color Figures]

Color copies of photomicrograph figures that accompany a report studying uranium in granites in the southwestern United States.
Date: October 1980
Creator: Silver, L. T.; Williams, I. S. & Woodhead, J. A.
Object Type: Image
System: The UNT Digital Library

Binary Phase Diagrams of Transition Elements

Chart issued by the U.S. National Bureau of Standards illustrating the systematic relationships between phase diagrams of transition elements. This chart includes color illustrations.
Date: May 1980
Creator: Waterstrat, Richard M.
Object Type: Poster
System: The UNT Digital Library
Corrosion Behavior of Several Metals in Ethylene Glycol-Base Heat-Transfer Fluids under Conditions Encountered in Solar Energy Systems (open access)

Corrosion Behavior of Several Metals in Ethylene Glycol-Base Heat-Transfer Fluids under Conditions Encountered in Solar Energy Systems

The corrosion behavior of aluminum, copper, and iron in inhibited ethylene glycol-ASTM corrosive water solutions was evaluated in a laboratory loop under isothermal and heat-flux conditions for 1000 h at temperatures between 378 and 413 degrees K, in static autoclave tests at 450 degrees K for 500 h, and by potentiodynamic polarization measurements at temperatures between 298 and 348 degrees K. The effect of time, temperature, and ethylene glycol concentration of the heat-transfer fluid on the extent of inhibitor depletion was determined from analyses of the reserve alkalinity, pH, and inhibitor content of the solutions. The performance of an electrochemical sensor as a monitor of fluid quality was also evaluated. A heat flux of 0.4 to 1.0 kW/m sq. did not have a significant effect on the corrosion behavior of the various materials at temperatures between 378 and 413 degrees K. The corrosion rates of aluminum, copper, and iron in the 50 volume percent inhibited ethylene glycol-corrosive water solution decreased as a function of time during the 1000-h test. At 413 degrees K, the corrosion rate of copper was considerably higher than that of iron or aluminum at low flow velocity. Significant degradation of the fluid quality, as indicated by …
Date: January 1980
Creator: Zeman, G. J.
Object Type: Report
System: The UNT Digital Library
Experiments on Cold-Trap Regeneration by NaH Decomposition (open access)

Experiments on Cold-Trap Regeneration by NaH Decomposition

Cold-trap regeneration may be very important in future LMFBRs because of the expected high hydrogen source from the steam generators. This hydrogen precipitates as NaH in the cold trap and may fill the trap within one year of operation. Several methods of cold-trap regeneration were considered, but the simplest and least expensive appears to be decomposition of NaH under vacuum at elevated temperatures. Experiments were done to assess the feasibility of this method for cold-trap regeneration. Small-scale simulated cold traps (SCT) were loaded with NaH and NaH plus Na2O, and were heated both under vacuum and under a sweep gas at 100 kPa. The evolved hydrogen was converted to water by a CuO bed and collected in a weighing tube.
Date: June 1980
Creator: Argonne National Laboratory. Chemical Engineering Division.
Object Type: Report
System: The UNT Digital Library
Branching Fraction in the Radioactive Decay of ⁸⁵mKr (open access)

Branching Fraction in the Radioactive Decay of ⁸⁵mKr

The branching fraction in the decay of the fission product ⁸⁵m-krypton⁸⁵m to the ground state ⁸⁵krypton (10.75 y) was measured relative to the total decay to both ⁸⁵krypton and ⁸⁵Rb. Samples of uranium-235 were highly irradiated in a high-flux reactor and dissolved. ⁸⁵Rb was measured by isotope-dilution mass spectrometry, and the ⁸⁵krypton was counted in GM tubes the counting efficiencies of which were calibrated with a standardized ⁸⁵krypton gas of known disintegration rate. The branching fraction measured with both a low-burnup sample and a high-burnup sample was 0.2160 +/- 0.0019, the largest error arising from the uncertainty in the caibration of the standardized gas.
Date: February 1980
Creator: Jaffey, A. H.; Steinberg, E. P.; Gindler, J. E.; Gray, J.; Horwitz, E. P.; Hughes, J. P. et al.
Object Type: Report
System: The UNT Digital Library
Corrosion and Mechanical Behavior of Materials for Coal Gasification Applications (open access)

Corrosion and Mechanical Behavior of Materials for Coal Gasification Applications

A state-of-the-art review is presented on the corrosion and mechanical behavior of materials at elevated temperatures in coal-gasification environments. The gas atmosphere in coal-conversion processes are, in general, complex mixtures which contain sulfur-bearing components (hydrogen sulfide, SO2, and COS) as well as oxidants (carbon dioxide/carbon monoxide and water/hydrogen). The information developed over the last five years clearly shows sulfidation to be the major mode of material degradation in these environments. The corrosion behavior of structural materials in complex gas environments is examined to evaluate the interrelationships between gas chemistry, alloy chemistry, temperature, and pressure. Thermodynamic aspects of high-temperature corrosion processes that pertain to coal conversion are discussed, and kinetic data are used to compare the behavior of different commercial materials of interest. The influence of complex gas environments on the mechanical properties such as tensile, stress-rupture, and impact on selected alloys is presented. The data have been analyzed, wherever possible, to examine the role of environment on the property variation. The results from ongoing programs on char effects on corrosion and on alloy protection via coatings, cladding, and weld overlay are presented. Areas of additional research with particular emphasis on the development of a better understanding of corrosion processes in …
Date: May 1980
Creator: Natesan, K.
Object Type: Report
System: The UNT Digital Library
SACO-1: a Fast-Running LMFBR Accident-Analysis Code (open access)

SACO-1: a Fast-Running LMFBR Accident-Analysis Code

SACO is a fast-running computer code that simulates hypothetical accidents in liquid-metal fast breeder reactors to the point of permanent subcriticality or to the initiation of a prompt-critical excursion. In the tradition of the SAS codes each sub-assembly is modeled by a representative fuel pin with three distinct axial regions to simulate the blanket and core regions. However, analytic and integral models are used wherever possible to cut down the computing time and storage requirements. The physical models and basic equations are described in detail.
Date: January 1980
Creator: Mueller, C. J.; Cahalan, J. E. & Vaurio, J. K.
Object Type: Report
System: The UNT Digital Library
COMMIX-SA-1: a Three-Dimensional Thermohydrodynamic Computer Program for Solar Applications (open access)

COMMIX-SA-1: a Three-Dimensional Thermohydrodynamic Computer Program for Solar Applications

COMMIX-SA-1 is a three-dimensional, transient, single-phase, compressible-flow, component computer program for thermohydrodynamic analysis. It was developed for solar applications in general, and for analysis of thermocline storage tanks in particular. The conservation equations (in cylindrical coordinates) for mass, momentum, and energy are solved as an initial-boundary-value problem. The detailed numerical-solution procedure based on a modified ICE (Implicit Continuous-Fluid Eulerian) technique is described. A method for treating the singularity problem arising at the origin of a cylindrical-coordinate system is presented. In addition, the thermal interactions between fluid and structures (tank walls, baffles, etc.) are explicitly accounted for. Finally, the COMMIX-SA-1 code structure is delineated, and an input description and sample problems are presented.
Date: November 1980
Creator: Sha, W. T.; Lin, E. I. H.; Schmitt, R. C.; Liu, K. V.; Hull, J. R.; Oras, J. J., Jr. et al.
Object Type: Report
System: The UNT Digital Library
The Delayed-Neutron Fraction in a Pulsed Spallation Neutron Source (open access)

The Delayed-Neutron Fraction in a Pulsed Spallation Neutron Source

The fraction of delayed neutrons beta in slow-neutron beams from a uranium-238 pulsed spallation neutron source is 0.0053 for 300 MeV protons. This measurement appears to be the first one of this quantity. The result indicates that, for most classes of measurements, the delayed-neutron background in time-of-flight instruments will be unimportant, and places constraints on the physics description of spallation targets. The measurement was performed at the prototype pulsed spallation neutron source, ZING-P', at Argonne National laboratory.
Date: February 1980
Creator: Carpenter, J. M.
Object Type: Report
System: The UNT Digital Library
Fast Critical Assembly Safeguards Summary Report, October 1978 - September 1979, Volume 1 (open access)

Fast Critical Assembly Safeguards Summary Report, October 1978 - September 1979, Volume 1

Nuclear material inventory verification techniques for large split-table type fast critical assemblies are being studied under this program. Emphasis has been given to techniques that minimize fuel handling in order to reduce facility down time and radiation exposure to the inventory team. The techniques studied include autoradiography, reactivity, and spectral index measurements.
Date: February 1980
Creator: Argonne National Laboratory
Object Type: Report
System: The UNT Digital Library
Fast Critical Assembly Safeguards. Summary Report, October 1978 - September 1979, Volume 2 (open access)

Fast Critical Assembly Safeguards. Summary Report, October 1978 - September 1979, Volume 2

PART 1: The effectiveness of a neutron well correlation counter (NWCC) and a random driver (RD) for plutonium-containing item assay and loss detection has been studied. The items were 4 in. x 2 in. x 1/4 in. stainless steel-clad metal plates and 6 in. x 3/8 in. stainless steel-clad oxide rods, each in two types of containment. PART 2: A neutron-counting/fuel-weighting system has been developed to provide the capability to assay the ZPR-6 and -9 plutonium fuel canisters rapidly and accurately. This system makes feasible the inline monitoring of fuel transfer from the storage vault to the fuel loading hoods and vice-versa. To exploit fully the system's potential, the equipment is intended to be used in conjunction with an on-line computer having a fuel and fuel-canister data base.
Date: September 1980
Creator: Winslow, G. H.; Bellinger, F. O.; Scharping, R. A.; Rusch, G. K. & Groh, E. F.
Object Type: Report
System: The UNT Digital Library
Fast Critical Assembly Safeguards: NDA Methods for Highly Enriched Uranium. Summary Report, October 1978 - September 1979, Volume 3 (open access)

Fast Critical Assembly Safeguards: NDA Methods for Highly Enriched Uranium. Summary Report, October 1978 - September 1979, Volume 3

Nondestructive assay (NDA) methods, principally passive gamma measurements and active neutron interrogation, have been studied for their safeguards effectiveness and programmatic impact as tools for making inventories of highly enriched uranium fast critical assembly fuel plates. It was concluded that no NDA method is the sole answer to the safeguards problem, that each of those emphasized here has its place in an integrated safeguards system, and that each has minimum facility impact.
Date: December 1980
Creator: Bellinger, F. O. & Winslow, G. H.
Object Type: Report
System: The UNT Digital Library
Conceptual Design of Electrical Balance of Plant for Advanced Battery Energy Storage Facility. Annual Report March 1979 (open access)

Conceptual Design of Electrical Balance of Plant for Advanced Battery Energy Storage Facility. Annual Report March 1979

Large-scale efforts are in progress to develop advanced batteries for utility energy storage systems. Realization of the full benefits available from those systems requires development, not only of the batteries themselves, but also the ac/dc power converter, the bulk power interconnecting equipment, and the peripheral electric balance of plant equipment that integrate the battery/converter into a properly controlled and protected energy system. This study addresses these overall system aspects; although tailored to a 20-MW, 100-MWh lithium/sulfide battery system, the technology and concepts are applicable to any battery energy storage system.
Date: January 1980
Creator: King, Joseph M., Jr.; Vivirito, Joseph R. & Kornbrust, Frederick J.
Object Type: Report
System: The UNT Digital Library
Radiological and Environmental Research Division Annual Report: Part 1, Fundamental Molecular Physics, October 1979-September 1980 (open access)

Radiological and Environmental Research Division Annual Report: Part 1, Fundamental Molecular Physics, October 1979-September 1980

Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to molecular physics and chemistry. This report discusses the Section's work on the physics and chemistry of atoms, ions, and molecules - especially their interactions with external agents such as photons and electrons.
Date: 1980?
Creator: Argonne National Laboratory. Radiological and Environmental Research Division.
Object Type: Report
System: The UNT Digital Library
Fuel Cycle Programs, Quarterly Progress Report: April-June 1979 (open access)

Fuel Cycle Programs, Quarterly Progress Report: April-June 1979

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: September 1980
Creator: Steindler, M. J.; Ader, M.; Barletta, R. E.; Bates, J. K.; Bean, C. H.; Couture, R. A. et al.
Object Type: Report
System: The UNT Digital Library
Fuel Cycle Programs, Quarterly Progress Report: October-December 1979 (open access)

Fuel Cycle Programs, Quarterly Progress Report: October-December 1979

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: July 1980
Creator: Steindler, M. J.; Bates, J. K.; Couture, R. A.; Flynn, K. F.; Gerding, T. J.; Jardine, L. J. et al.
Object Type: Report
System: The UNT Digital Library
Materials Technology for Coal-Conversion Processes Quarterly Report: April-June 1980 (open access)

Materials Technology for Coal-Conversion Processes Quarterly Report: April-June 1980

Quarterly report on the activities of the Argonne National Laboratory Materials Science Division regarding studies on ceramic (refractory) and metallic materials presently being used or intended for use in coal-conversion processes. The program entails research in the fields of nondestructive testing and failure analysis, together with studies of erosive wear, corrosion, and refractory degradation.
Date: October 1980
Creator: Ellingson, W. A.
Object Type: Report
System: The UNT Digital Library
Materials Technology for Coal-Conversion Processes Quarterly Report: January-March 1980 (open access)

Materials Technology for Coal-Conversion Processes Quarterly Report: January-March 1980

Quarterly report on the activities of the Argonne National Laboratory Materials Science Division regarding economical conversion of coal into clean and usable alternate fuels will be advanced through the use of durable materials systems. This program is designed to provide part of the materials information necessary for successful operation of coal-conversion systems.
Date: June 1980
Creator: Argonne National Laboratory. Materials Science Division.
Object Type: Report
System: The UNT Digital Library
Post-Test Examinations of Li-Al/FeSx Secondary Cells (open access)

Post-Test Examinations of Li-Al/FeSx Secondary Cells

Post-test examinations were conducted to determine failure mechanisms, electrode morphologies, and in-cell corrosion of cell components, and to recommend appropriate design changes for improved cell performance and reliability. The reactive electrode materials required the design and construction of a special metallographic glovebox facility. Combinations of macro- and microscopic examinations determined that electrical short circuits were the predominant causes of cell failure. The major short circuit mechanism was extrusion of active material from one electrode and its subsequent contact with the opposing electrode (opposite polarity). Other mechanisms for short circuits included metallic deposits across separators, metallic deposits across the feed-through insulator (electrolyte leakage and corrosion), equipment malfunctions, cell assembly difficulties, etc. Post-test examinations confirmed that the short circuits were of mechanical origin; appropriate design changes were, therefore, recommended. Extensive microscopic examinations were conducted on both negative and positive electrodes to determine the morphology. Agglomeration of Li-Al was observed in the negative electrodes of most multi-plate cells. Examinations showed that the sulfides in the positive electrode remained as discrete particles in an electrolyte matrix. Also discussed are the results of post-test examinations to determine the following: lithium gradients in the negative electrodes, electrode expansion, materials distribution, copper deposition within electrode separators of …
Date: December 1980
Creator: Battles, J. E.; Mrazek, F. C. & Otto, N. C.
Object Type: Report
System: The UNT Digital Library
Development and Verification of the LIFE-GCFR Computer Code for Predicting Gas-Cooled Fast-Reactor Fuel-Rod Performance (open access)

Development and Verification of the LIFE-GCFR Computer Code for Predicting Gas-Cooled Fast-Reactor Fuel-Rod Performance

The fuel-pin modeling code LIFE-GCFR has been developed to predict the thermal, mechanical, and fission-gas behavior of a Gas-Cooled Fast Reactor (GCFR) fuel rod under normal operating conditions. It consists of three major components: thermal, mechanical, and fission-gas analysis. The thermal analysis includes calculations of coolant, cladding, and fuel temperature; fuel densification; pore migration; fuel grain growth; and plenum pressure. Fuel mechanical analysis includes thermal expansion, elasticity, creep, fission-product swelling, hot pressing, cracking, and crack healing of fuel; and thermal expansion, elasticity, creep, and irradiation-induced swelling of cladding. Fission-gas analysis simultaneously treats all major mechanisms thought to influence fission-gas behavior, which include bubble nucleation, resolution, diffusion, migration, and coalescence; temperature and temperature gradients; and fission-gas interaction with structural defects.
Date: December 1980
Creator: Hsieh, T. C.; Billone, Michael C. & Rest, J.
Object Type: Report
System: The UNT Digital Library
Materials Technology for Coal-Conversion Processes Quarterly Report: October-December 1980 (open access)

Materials Technology for Coal-Conversion Processes Quarterly Report: October-December 1980

Quarterly report on the activities of the Argonne National Laboratory Materials Science Division regarding an examination of cores taken from the slag-refractory interface of seven refractories.
Date: 1980
Creator: Ellingson, W. A.
Object Type: Report
System: The UNT Digital Library
User Guide for Minpack-1 (open access)

User Guide for Minpack-1

MINPACK-1 is a pack of FORTRAN subprograms for the numerical solution of nonlinear equations and nonlinear least-squares problems. This report provides an overview of the algorithms and software in the package, and includes the documentation and program listings.
Date: August 1980
Creator: Moré, Jorge J.; Garbow, Burton S. & Hillstrom, Kenneth E.
Object Type: Report
System: The UNT Digital Library
Automatic Transformations in the Inference Process (open access)

Automatic Transformations in the Inference Process

A technique for incorporating automatic transformations into processes such as the application of inference rules, subsumption, and demodulation provides a mechanism for improving search strategies for theorem proving problems arising from the field of program verification. The incorporation of automatic transformations into the inference process can alter the search space for a given problem, and is particularly useful for problems having broad rather than deep proofs. The technique can also be used to permit the generation of inferences that might otherwise be blocked and to build some commutativity or associativity into the unification process. Appropriate choice of transformations, and new literal clashing and unification algorithms for applying them, showed significant improvement on several real problems according to several distinct criteria.
Date: July 1980
Creator: Veroff, Robert L.
Object Type: Report
System: The UNT Digital Library