Annual report providing tabular statistical information about motor vehicle accidents that directly or indirectly involved school buses in Texas during calendar year 1983, with data broken out by various criteria including number of persons, locations, types of accidents, time of day, and other factors.

Monthly report providing tabular statistical information about motor vehicle accidents in Texas during 1984, with data broken out by various criteria including number of persons, locations, types of accidents, time of day, and other factors.

Annual report providing tabular statistical information about motor vehicle accidents in Texas during calendar year 1983, with data broken out by various criteria including number of persons, locations, types of accidents, time of day, and other factors.

Monthly report providing tabular statistical information about motor vehicle accidents in rural areas of Texas during 1984, with data broken out by various criteria including number of persons, locations, types of accidents, time of day, and other factors.

Annual report providing tabular statistical information about motor vehicle accidents in rural areas of Texas during calendar year 1983, with data broken out by various criteria including number of persons, locations, types of accidents, time of day, and other factors.

Monthly report detailing all Texas automobile, pickup, and motorcycle theft data, broken down into tabular lists according to various criteria.

Report presenting petrographic descriptions of eight rock samples collected at or near the Tusas Mountain Granite and Maquinita Granodorite areas surveyed for the National Uranium Resource Evaluation (NURE) survey, listing the rock name, percentage of mineral components, and features of each rock.

Report presenting petrographic descriptions of eleven rock samples collected at or near the Venado Creek area surveyed for the National Uranium Resource Evaluation (NURE) survey, listing the rock name, percentage of mineral components, and features of each rock.

Report presenting petrographic descriptions of five rock samples collected at or near the Pedad claims area surveyed for the National Uranium Resource Evaluation (NURE) survey, listing the rock name, percentage of mineral components, and features of each rock.

Charts providing petrographic descriptions of rock samples obtained in the Waterloo Gulch drainage, listing the rock name, percentage of mineral components, and features of each rock.

Report describing the petrography of seven rhyolite specimens and one basalt specimen from China Hat, China Cap, and North Cone areas surveyed for the National Uranium Resource Evaluation (NURE) survey.

Report providing a background summary of the potential sitting areas for a low-level radioactive waste disposal facility and a thorough study of the possible site location.

Report investigating the economic impact of radioactive waste disposal sites in Texas, specifically counties: Borden, Lamar, Zavala, Dimmit, and Hudspeth.

Narrative report documenting ecological characterization to determine socioeconomic and natural features influencing the Texas Gulf coast region, as part of a larger land-use planning project.

A report with the purpose of cartographically rendering those known biological resources of the Texas coastal areas which might influence coastal land-use decisions.

A report with the purpose of cartographically rendering those know aspects of the natural and cultural features of the Texas costal areas which might influence land decisions.

This report contains the individual reports of subsequent field investigations conducted in five areas that contain anomalously high contents of uranium, based upon radiometric and geochemical surveys and geologic investigations data made by HSSR/ARR and/or other geologic data.

This interim report documents work carried out by Combustion Engineering, Inc. under a contract to Exxon Research and Engineering Company to develop a conceptual Hybrid Boiler design fueled by the vacuum distillation residue (vacuum bottoms) derived from Illinois No. 6 coal in the EDS Coal Liquefaction Process. This report was prepared by Combustion Engineering, Inc., and is the first of two reports on the predevelopment phase of the Hybrid Boiler program. This report covers the results of a laboratory investigation to assess the fuel and ash properties of EDS vacuum bottoms. The results of the laboratory testing reported here were used in conjunction with Combustion Engineering's design experience to predict fuel performance and to develop appropriate boiler design parameters. These boiler design parameters were used to prepare the engineering design study reported in EDS Interim Report FE-2893-113, the second of the two reports on the predevelopment phase of the Hybrid Boiler Program. 46 figures, 29 tables.

All objectives in the EDS Cooperative Agreement for Phases III-B through V have been achieved for the RCLU pilot plants. EDS operations have been successfully demonstrated in both the once-through and bottoms recycle modes for coals of rank ranging from bituminous to lignitic. An extensive data base detailing the effects of process variable changes on yields, conversions and product qualities for each coal has been established. Continuous bottoms recycle operations demonstrated increased overall conversion and improved product slate flexibility over once-through operations. The hydrodynamics of the liquefaction reactor in RCLU were characterized through tests using radioactive tracers in the gas and slurry phases. RCLU was shown to have longer liquid residence times than ECLP. Support work during ECLP operations contributed to resolving differences between ECLP conversions and product yields and those of the small pilot plants. Solvent hydrogenation studies during Phases IIIB-V of the EDS program focused on long term activity maintenance of the Ni-MO-10 catalyst. Process variable studies for solvents from various coals (bituminous, subbituminous, and lignitic), catalyst screening evaluations, and support of ECLP solvent hydrogenation operations. Product quality studies indicate that highly cyclic EDS naphthas represent unique and outstanding catalytic reforming feedstocks. High volumes of high octane motor …

A series of parametric calculations was run with the S-CUBED geopressured-geothermal simulator MUSHRM to assess the effects of important formation, fluid and well parameters on brine and gas recovery from geopressured reservoir systems. The specific parameters considered are formation permeability, pore-fluid salinity, temperature and gas content, well radius and location with respect to reservoir boundaries, desired flow rate, and possible shale recharge. It was found that the total brine and gas recovered (as a fraction of the resource in situ) were most sensitive to formation permeability, pore-fluid gas content, and shale recharge.

A fractional factorial experimental design was used to determine the maximum production and photosynthetic efficiency that could be achieved in shallow algal mass culture systems (SAMCS) of the marine diatom Phaeodactylum tricornutum. Dilution rate and CO/sub 2/ supply were found to be the most important system parameters. Maximum production was found to be about 25 g dry wt m/sup -2/d/sup -1/. This production corresponded to a photosynthetic efficiency of 5.6%. These figures are 50 to 100% better than the production rates achieved in earlier P. tricornutum cultures using conventional culture techniques. The results are consistent with a theoretical model of the impact of the flashing light effect on algal mass culture production. This model predicts that at the typical irradiances in Hawaii, full utilization of the flashing light effect should enhance production by 70% to over 200%. It was concluded that the use of foil arrays in the experimental flume creates systematic vertical mixing on a time scale suitable for utilizing the flashing light effect. Production of P. tricornutum culture is probably limited by temperature. P. tricornutum cannot survive at temperatures in excess of 25/sup 0/C in outdoor mass cultures. Growth of mesophilic species in the temperature range 30 to …

The Steam Generator Group Project (SGGP) is an NRC program joined by additional sponsors. The SGGP utilizes a steam generator removed from service at a nuclear plant (Surry 2) as a vehicle for research on a variety of safety and reliability issues. This report is an annual summary of progress of the program for 1982. Information is presented on the Steam Generator Examination Facility (SGEF), especially designed and constructed for this research. Loading of the generator into the SGEF is then discussed. The report then presents radiological field mapping results and personnel exposure monitoring. This is followed by information on field reduction achieved by channel head decontaminations. The report then presents results of a secondary side examination through shell penetrations placed prior to transport, confirming no change in generator condition due to transport. Decontamination of the channel head is discussed followed by plans for eddy current testing and removal of the plugs placed during service. Results of a preliminary profilometry examination are then provided.

Analyses of sludge and soluble waste samples and the inventory of sludge and soluble waste have been used to estimate the concentration of technetium-99 (Tc-99) in sludge solids and soluble waste. These data were also used to establish if the source term assumptions for Tc-99 in the Defense waste Processing Facility (DWPF) flowsheet are accurate and determine the fraction of the Tc-99 inventory in the waste that is soluble. This analysis was needed to establish if the present basis for decontaminated salt feed to the saltstone process is correct. These results and the projected leach rate for Tc-99 from saltstone can then be used to establish if Tc-99 must be removed from contaminated supernate.

Long-lived isotopes in nuclear waste can have the greatest impact on man and the environment because of the integrated dose over a long time period. Many long-lived radioactive isotopes are present in the waste at Savannah River Plant. Actinide elements make up a significant portion of these isotopes. But when the waste is incorporated into a glass waste form, the actinides are converted to chemically stable oxide species that are released at extremely low and controlled rates, even after the waste form has degraded. Because of their different chemistry, radioactive isotopes of carbon, technetium, and iodine could be released at a significantly higher rate. To establish the potential hazard from these isotopes, their concentration in waste forms for final disposal must be known. The concentrations of C-14 and T{sub c}-99 in SRP waste were previously estimated. Additional analytical data has now been obtained for I-129 in H-Area soluble waste to estimate its concentration in SRP waste. Because of the nature of processes at SRP, most of the I-129 in the waste is in the H-Area waste tanks.