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Slip-and-Fall Accidents During Equipment Maintenance in the Surface Mining Industry

Description: Report issued by the U.S. Bureau of Mines discussing mining accidents during equipment maintenance. As stated in the abstract, "this U.S. Bureau of Mines report identifies potential causes of slip-and-fall accidents occurring during surface mine equipment maintenance and describes the relative roles of direct worker behavior and machine design" (p. 1). This report includes tables, and illustrations.
Date: 1990
Creator: Albin, Thomas J. & Adams, W. P.
Partner: UNT Libraries Government Documents Department

Taller de Trabajo sobre evaluación de los Efectos Ecológicos de los Cambios Climáticos Globales

Description: This report discusses the Ecological Effects Assessment of Climatic changes in Venezuela Workshop, organized by the PAN-EARTH Project and the Centre for Ecology of the Venezuelan Institute for Scientific Research (IVIC). The main objective was the evaluation of the effects of climate changes on the main ecosystems in Venezuela using ecological models.
Date: July 1990
Creator: Acevedo, Miguel F.; Andressen, Rigoberto; Arends, Ernesto; Azocar, Aura; Borges, Felix; Corvo, Fernando et al.
Partner: UNT College of Engineering

HFBR: Review of the technical specifications against the FSAR

Description: The purpose of this review is to determine the adequacy of the High Flux Beam Reactor (HFBR) Technical Specifications for 40 MW operation by comparison with the HFBR Final Safety Analysis Report, particularly the accident analyses chapter. Specifically, the Technical Specifications were compared against the Design Basis Accident (DBA) Analyses presented in the Addendum to the HFBR FSAR for 60 MW Operation. The 60 MW DBA analyses was used since it is more current and complete than the analyses presented in the original FSAR which is considered obsolete. A listing of the required systems and equipment was made for each of the accidents analyzed. Additionally, the Technical Specification instrument setpoints were compared to the DBA analyses parametric values. Also included in this review was a comparison of the Technical Specification Bases against the FSAR and the identification of any differences. The HFBR Operations Procedures Manual (OPM) was also reviewed for any inconsistencies between the FSAR or the Technical Specifications. Upon completion of this review it was determined that the Technical Specifications are well written and the items commented on should not delay the low power restart (40 MW). Additionally, the OPM is also well written and does not require further modification before restart.
Date: January 25, 1990
Creator: Rao, D.V.; Ross, S.B.; Claiborne, E.R.; Darby, J.L. & Clark, R.A.
Partner: UNT Libraries Government Documents Department

CURE: Clean use of reactor energy

Description: This paper presents the results of a joint Westinghouse Hanford Company (Westinghouse Hanford)-Pacific Northwest Laboratory (PNL) study that considered the feasibility of treating radioactive waste before disposal to reduce the inventory of long-lived radionuclides, making the waste more suitable for geologic disposal. The treatment considered here is one in which waste would be chemically separated so that long-lived radionuclides can be treated using specific processes appropriate for the nuclide. The technical feasibility of enhancing repository performance by this type of treatment is considered in this report. A joint Westinghouse Hanford-PNL study group developed a concept called the Clean Use of Reactor Energy (CURE), and evaluated the potential of current technology to reduce the long-lived radionuclide content in waste from the nuclear power industry. The CURE process consists of three components: chemical separation of elements that have significant quantities of long-lived radioisotopes in the waste, exposure in a neutron flux to transmute the radioisotopes to stable nuclides, and packaging of radionuclides that cannot be transmuted easily for storage or geologic disposal. 76 refs., 32 figs., 24 tabs.
Date: May 1, 1990
Partner: UNT Libraries Government Documents Department

Manganese-oxide minerals in fractures of the Crater Flat Tuff in drill core USW G-4, Yucca Mountain, Nevada

Description: The Crater Flat Tuff is almost entirely below the water table in drill hole USW G-4 at Yucca Mountain, Nevada. Manganese-oxide minerals from the Crater Flat Tuff in USW G-4 were studied using optical, scanning electron microscopic, electron microprobe, and x-ray powder diffraction methods to determine their distribution, mineralogy, and chemistry. Manganese-oxide minerals coat fractures in all three members of the Crater Flat Tuff (Prow Pass, Bullfrog, and Tram), but they are most abundant in fractures in the densely welded devitrified intervals of these members. The coatings are mostly of the cryptomelane/hollandite mineral group, but the chemistry of these coatings varies considerably. Some of the chemical variations, particularly the presence of calcium, sodium, and strontium, can be explained by admixture with todorokite, seen in some x-ray powder diffraction patterns. Other chemical variations, particularly between Ba and Pb, demonstrate that considerable substitution of Pb for Ba occurs in hollandite. Manganese-oxide coatings are common in the 10-m interval that produced 75% of the water pumped from USW G-4 in a flow survey in 1983. Their presence in water-producing zones suggests that manganese oxides may exert a significant chemical effect on groundwater beneath Yucca Mountain. In particular, the ability of the manganese oxides found at Yucca Mountain to be easily reduced suggests that they may affect the redox conditions of the groundwater and may oxidize dissolved or suspended species. Although the Mn oxides at Yucca Mountain have low exchange capacities, these minerals may retard the migration of some radionuclides, particularly the actinides, through scavenging and coprecipitation. 23 refs., 21 figs., 2 tabs.
Date: July 1, 1990
Creator: Carlos, B.A.; Bish, D.L. & Chipera, S.J.
Partner: UNT Libraries Government Documents Department

Numerical simulation of gas flow through unsaturated fractured rock at Yucca Mountain, Nevada

Description: Numerical analysis is used to identify the physical phenomena associated with barometrically driven gas (air and water vapor) flow through unsaturated fractured rock at Yucca Mountain, Nevada. Results from simple finite difference simulations indicate that for a fractured rock scenario, the maximum velocity of air out of an uncased 10 cm borehole is 0.002 m s{sub {minus}1}. An equivalent porous medium (EPM) model was incorporated into a multiphase, multicomponent simulator to test more complex conceptual models. Results indicate that for a typical June day, a diurnal pressure wave propagates about 160 m into the surrounding Tiva Canyon hydrogeologic unit. Dry air that enters the formation evaporates water around the borehole which reduces capillary pressure. Multiphase countercurrent flow develops in the vicinity of the hole; the gas phase flows into the formation while the liquid phase flows toward the borehole. The effect occurs within 0.5 m of the borehole. The amount of water vapor leaving the formation during 1 day is 900 cm{sup 3}. This is less than 0.1% of the total recharge into the formation, suggesting that the barometric effect may be insignificant in drying the unsaturated zone. However, gas phase velocities out of the borehole (3 m s{sup {minus}1}), indicating that observed flow rates from wells along the east flank of Yucca Mountain were able to be simulated with a barometric model.
Date: January 1, 1990
Creator: Cooper, C.A.
Partner: UNT Libraries Government Documents Department

A study of the source materials, depositional environments, mechanisms of generation and migration of oils in the Anadarko, Oklahoma. Progress report, September 15, 1990--September 14, 1991

Description: This report is for the final year of a three-year funded project. A new proposal has been submitted and it is hoped that funding will continue for another three years. It is felt that good progress is being made with our work on studying the oils and source rocks in the Anadarko Basin. Furthermore a number of associated projects have evolved during this period which have also produced many useful results and various analytical methods have been developed. In Appendix I lists of students totally or partially supported by this work plus various publications are given. It is hoped that these will testify to our productivity arising from the DOE support over the past few years.
Date: April 20, 1990
Creator: Philp, R.P.
Partner: UNT Libraries Government Documents Department

Program status 2. quarter -- FY 1990: Fusion technology development

Description: During this period, the ARIES-I blanket design team has concentrated its efforts on preparation of the final report. For the ARIES-II blanket design, two concepts are being evaluated. They are the Li self-cooled and the helium-cooled lithium breeder designs. The scoping design of the second concept has been completed. Varian EIMAC has had two tube failures in trying to assemble the X2274 tetrodes for the tests in Japan. Despite the failures it is still possible for the tubes to be ready as scheduled. Also during this quarter, the joint US/PRC integral experiment on beryllium was completed in March and the analysis of results has begun. Finally, the final design of DIII-D Divertor Material Exposure System (DiMES) was completed. Preliminary analysis by ANL of DIII-D divertor erosion, using measured plasma conditions, predicts maximum net erosion of 50 {micro}m and maximum net deposition of 23 {micro}m. Measurement by SNL-L of the 12 tiles removed in December 1989 is still pending.
Date: May 1, 1990
Partner: UNT Libraries Government Documents Department

JASPER [Japanese-American Shielding Program of Experimental Research], USDOE/PNC shielding research program: Analysis of the JASPER fission gas plenum experiment

Description: The results of the analysis of the Fission Gas Plenum Experiment are presented. This experiment is the second in a series of several experiments comprising a joint US DOE-Japan PNC Shielding Research Program (JASPER). The four Fission Gas Plenum Experiment configurations, designed for the measurement of neutron streaming through the fission gas plenum region, were analyzed using Monte Carlo and two-dimensional discrete ordinated methods. Calculated results compared well with measured results in many cases, although results were consistently underpredicted for the shorter plenum configurations. Like the measured data, the calculated results indicated no significant streaming when results from the heterogeneous mockups were compared to those from the homogeneous mockups. An explanation is given as to why little streaming was observed. The Hornyak button dose rates were overpredicted because of a normalization problem with the response function but yielded horizontal traverse curves whose shapes agreed well with the measured shapes to the same extent as did those for the other integral detectors. 16 refs., 16 figs., 4 tabs.
Date: May 1, 1990
Creator: Slater, C.O.
Partner: UNT Libraries Government Documents Department

IMGA [Irradiated Microsphere Gamma Analyzer] examination of the Set No. 4 fuel under project work statement FD-20

Description: Results of an examination of over 10,800 unbonded fuel particles from three irradiated spherical fuel elements by the Irradiated Microsphere Gamma Analyzer system are reported. The investigation was initiated to assess fission product behavior in LEU UO{sub 2} TRISO-coated fuel particles at elevated temperatures. Of the three spheres considered, one was reserved as a control and the other two were subjected to simulated accident-condition temperatures of 1600{degree}C and 1800{degree}C, respectively. For the control sphere and the sphere tested at 1600{degree}C, no statistical evidence of fission product release (cesium) from individual particles was observed. At fuel temperatures of 1800{degree}C, however, fission product release (cesium) from individual particles was significant and there was large particles-to-particle variation. At 1800{degree}C, individual particle release (cesium) was on average ten times the Kernforschungsanlage-measured integral spherical fuel element release value. Particle release data from the sphere tested at 1800{degree}C indicate that there may be two distinct modes of failure at fuel temperatures of 1800{degree}C and above. 5 refs., 9 figs., 9 tabs.
Date: March 1, 1990
Creator: Baldwin, C.A. & Kania, M.J.
Partner: UNT Libraries Government Documents Department

Fifteenmile Basin Habitat Enhancement Project: Annual Report FY 1990.

Description: The goal of the Fifteenmile Creek Habitat Improvement project is to improve wild winter steelhead habitat in the Fifteenmile Creek Basin. This goal was addressed under the Columbia River Basin Fish and Wildlife Program, Measure 703 (c) (1) - Action Item 4.2. Construction of fish habitat structures was completed on approximately 3.5 miles of Eightmile Creek and on approximately 8.5 miles of Fifteenmile Creek. A total of 15,435 yds of rock was placed to improve rearing and spawning habitat, and to improve water quality and reduce siltation. Riparian protection fencing was completed on 1.8 miles of Dry Creek, approximately 1.75 miles on Eightmile Creek, and 4.75 miles on Fifteenmile Creek. Approximately 10 miles of stream will receive protection from the 8 miles of new fencing installed and 6.5 miles of abandoned fence repaired. Irrigation withdrawal screens were installed at six irrigation pump withdrawals. These screens functioned satisfactorily during the irrigation season. Physical and biological monitoring of stream flows, water temperature, and macro-invertebrate communities was conducted.
Date: March 31, 1990
Creator: Smith, Roger C. & Brown, Lawrence F.
Partner: UNT Libraries Government Documents Department

An analysis of repository waste-handling operations

Description: This report has been prepared to document the operational analysis of waste-handling facilities at a geologic repository for high-level nuclear waste. The site currently under investigation for the geologic repository is located at Yucca Mountain, Nye County, Nevada. The repository waste-handling operations have been identified and analyzed for the year 2011, a steady-state year during which the repository receives spent nuclear fuel containing the equivalent of 3000 metric tons of uranium (MTU) and defense high-level waste containing the equivalent of 400 MTU. As a result of this analysis, it has been determined that the waste-handling facilities are adequate to receive, prepare, store, and emplace the projected quantity of waste on an annual basis. In addition, several areas have been identified where additional work is required. The recommendations for future work have been divided into three categories: items that affect the total waste management system, operations within the repository boundary, and the methodology used to perform operational analyses for repository designs. 7 refs., 48 figs., 11 tabs.
Date: September 1, 1990
Creator: Dennis, A.W.
Partner: UNT Libraries Government Documents Department

Program status 3. quarter -- FY 1990: Fusion technology development

Description: During this period, the ARIES-I blanket design team completed the preparation of the ARIES-I reactor design final report. The helium-cooled, lithium breeder, SiC composite structure blanket option for the ARIES-II was evaluated and it was found that the corrosion resistance of the SiC in lithium is very poor. At the direction of DOE/OFE, the ARIES team was directed to defer work on the ARIES-II and to begin work immediately on the ARIES-III advanced fuel (D-{sup 3}He) tokamak design. Also, Varian EIMAC completed fabrication of two X2274 tetrode tubes and shipped them to Japan for testing on schedule. JAERI carried out the testing and both tubes operated successfully above specifications. The US and Chinese beryllium shells were shipped to Osaka University in Japan, beginning the second phase of the ``Coordinated U.S./PRC, U.S./Japan and Japan/PRC Fusion Neutron Integral Experiments.`` New fusion nuclear data experiments are being initiated for O(n,alpha) and Tc{sup 99}(n,p) cross section. Finally, the design and installation of the DiMES in-vessel components on DIII-D was completed.
Date: July 24, 1990
Partner: UNT Libraries Government Documents Department

Predictive modelling of boiler fouling. Final report.

Description: A spectral element method embodying Large Eddy Simulation based on Re- Normalization Group theory for simulating Sub Grid Scale viscosity was chosen for this work. This method is embodied in a computer code called NEKTON. NEKTON solves the unsteady, 2D or 3D,incompressible Navier Stokes equations by a spectral element method. The code was later extended to include the variable density and multiple reactive species effects at low Mach numbers, and to compute transport of large particles governed by inertia. Transport of small particles is computed by treating them as trace species. Code computations were performed for a number of test conditions typical of flow past a deep tube bank in a boiler. Results indicate qualitatively correct behavior. Predictions of deposition rates and deposit shape evolution also show correct qualitative behavior. These simulations are the first attempts to compute flow field results at realistic flow Reynolds numbers of the order of 10{sup 4}. Code validation was not done; comparison with experiment also could not be made as many phenomenological model parameters, e.g., sticking or erosion probabilities and their dependence on experimental conditions were not known. The predictions however demonstrate the capability to predict fouling from first principles. Further work is needed: use of large or massively parallel machine; code validation; parametric studies, etc.
Date: December 31, 1990
Creator: Chatwani, A
Partner: UNT Libraries Government Documents Department

Results of design calculations for the modulator of the crossed field undulator device

Description: The modulator is a five pole wiggler with a fixed 5 cm gap. In the current design, the modulator is oriented so that the magnetic field in the device is parallel to the field in one of the undulators. The two end poles have no coil and are only half as thick as the inner poles. The end poles serve as field clamps that reduce the stray field of the modulator and the sextupole coefficient of the field integral. The center pole and the two side poles can be energized with coils. As long as the permeability is large enough within the steel the current in the center coil should be twice the current in a side coil to avoid steering the electron beam. Therefore, if the center coil has twice as many turns as the side coil, the magnet can be driven by one power supply.
Date: August 1, 1990
Creator: Sovay, R.
Partner: UNT Libraries Government Documents Department

Mathematical and geological approaches to minimizing the data requirements for statistical analysis of hydraulic conductivity distribution. Annual report

Description: The following research was completed: refinement of air-pereameter design, calibration; collection of air-flow-rate data at the facies scale; mapping of depositional facies at an outcrop west of Belen, New Mexico; delineation of permeability facies from mapped depositional facies and geostatitistical analysis of air-flow-rate data observed at the facies scale (Sierra Ladrones formation); and evaluation of threshold-crossing theory.
Date: August 1, 1990
Creator: Phillips, F.M. & Wilson, J.L.
Partner: UNT Libraries Government Documents Department

The TEAM workshops: A short history

Description: Early in 1985, Sam Berk of the Office of Fusion Energy, US Department of Energy, suggested that the development and validation of 3-D eddy current codes would benefit from the compilation of benchmark problems that could be used to validate the codes and from a series of workshops for the comparison of solution methods and codes. (Two years later, at the first International Symposium on Fusion Nuclear Technology in Tokyo, Sam Berk proposed the acronym TEAM for the workshops.) At a three-day planning meeting at Argonne National Laboratory (ANL) in November 1985, eleven participants from five countries defined the goals, format, schedule and problems for the workshops. The ultimate goal is to show the effectiveness of numerical techniques and associated computer codes in solving electromagnetic field problems, and to gain confidence in their predictions. The workshops should also provide cooperation between workers, leading to an interchange of ideas. This note reviews the three cycles of workshops and the problems.
Date: August 28, 1990
Creator: Turner, L.R.
Partner: UNT Libraries Government Documents Department

1990 Fischer Standard study

Description: The purpose of this work is to develop a set of Titanium areal density standards for calibration and maintenance of the Fischer`s X-ray Fluorescence measurement system characterization curve program. The electron microprobe was calibrated for Titanium films on ceramic substrates using an existing set of laboratory standards (Quantity: 6 Range: 0.310 to 1.605). Fourteen source assemblies were measured and assigned values. These values are based on a mean calculation, of five separate readings, from best curve fit equations developed form the plot of the laboratory standards areal density (Source Measure) versus electron microprobe measurement (reading). The best fit equations were determined using the SAS General Linear Modeling (GLM) procedure. Four separate best fit equations were evaluated (Linear, Quadratic, Cubic and Exponential). Areal density values for the Fischer Standards appear here ordered by best fit equation based on maximum R{sup 2}.
Date: September 12, 1990
Creator: Roubik, G.J.
Partner: UNT Libraries Government Documents Department

Exploiting rod technology. Final report

Description: ROD development was proceeding apace until recent budgetary decisions caused funding support for ROD development to be drastically reduced. The funding which was originally provided by DARPA and the Balanced Technology Initiative (BTI) Office has been cut back to zero from $800K. To determine the aeroballistic coefficients of a candidate dart, ARDEC is currently supporting development out of its own 6.2 funds at about $100K. ARDEC has made slow progress toward achieving this end because of failures in the original dart during testing. It appears that the next dart design to be tested will diverge from the original concept visualized by DARPA and Science and Technology Associates (STA). STA, the design engineer, takes exception to these changes on the basis of inappropriate test conditions and insufficient testing. At this time, the full resolution of this issue will be difficult because of the current management structure, which separates the developer (ARDEC) from the designer (STA).
Date: June 1, 1990
Partner: UNT Libraries Government Documents Department

Capsule HRB-21 postirradiation examination plan

Description: Irradiation capsule HRB-21 is a test capsule designed to provide Modular High-Temperature Gas-Cooled Reactor (MHTGR) coated particle fuel performance data under test reactor conditions representative of normal MHTGR operation. The irradiated fuel will also be used for postirradiation heating in a controlled atmosphere allowing acquisition of fission product release data at sustained high temperatures. The in-reactor performance data, the postirradiation examination data, and the postirradiation heating data will be used for the validation of fuel performance models under normal and off-normal operating conditions. The accelerated irradiation is to take place in the High Flux Isotope Reactor (HFIR) at ORNL. This report identifies the procedures to be followed in carrying out the postirradiation disassembly and examination of HRB-21. Included is a description of the capsule, a detailed sequence of steps for disassembly of the capsule, a description of the postirradiation examination techniques to be employed, and specifications for the storage of capsule components and the reporting of results. 9 refs., 6 figs., 2 tabs.
Date: March 1, 1990
Creator: Packan, N.H.; Kania, M.J. & Shrader, L.G.
Partner: UNT Libraries Government Documents Department

Research development and demonstration of a fuel cell/battery powered bus system. Quarterly report, January 1--March 31, 1990

Description: This report describes the progress in the Georgetown University research, development and demonstration project of a fuel cell/battery powered bus system. The topics addressed in the report include vehicle design and application analysis, technology transfer activities, coordination and monitoring of system design and integration contractor, current problems, work planned, and manpower, cost and schedule reports.
Date: May 8, 1990
Creator: Romano, S. & Thelmo, J.R.
Partner: UNT Libraries Government Documents Department