Annual report providing tabular statistical information about motor vehicle accidents that directly or indirectly involved school buses in Texas during calendar year 1989, 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 that involved motorcycles in Texas during calendar year 1989, 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 1989, 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 1989, with data broken out by various criteria including number of persons, locations, types of accidents, time of day, and other factors.

The objectives of this study are to determine the intrinsic kinetics and the product layer diffusion rate by minimizing the resistances to gas-phase pore diffusion, and eliminating complications due to pore filling. In the report, a grain model was used to introduce the various potentially rate-limiting processes. It was compared with results obtained with a distributed pore model by Bhatia Perlmutter (1981). Comparing the predicted behavior of the surface areas with conversion, it was even possible to compare experimental results with other models. The conclusion of this study was that, even thought the kinetic parameters obtained with different samples differed much more if product layer diffusion assumed rate-limiting rather than the surface reaction, the shape of the predicted curve approached the experimental findings so much better, that product layer diffusion is indeed most likely to be rate-limiting. (VC)

This report is a needs assessment and project schedule for the Health Physics Analysis Laboratory (HPAL) upgrade project at Los Alamos National Laboratory (LANL). After reviewing current and projected HPAL operations, two custom-developed laboratory information management systems (LIMS) for similar facilities were reviewed; four commercially available LIMS products were also evaluated. This project is motivated by new regulations for radiation protection and training and by increased emphasis on quality assurance (QA). HPAL data are used to: protect the health of radiation workers; document contamination levels for transportation of radioactive materials and for release of materials to the public for uncontrolled use; and verify compliance with environmental emission regulations. Phase 1 of the HPAL upgrade project concentrates on four types of counting instruments which support in excess of 90% of the sample workload at the existing central laboratories. Phase 2 is a refinement phase and also integrates summary-level databases on the central Health, Safety, and Environment (HSE) VAX. Phase 3 incorporates additional instrument types and integrates satellite laboratories into the HPAL LIMS. Phase 1 will be a multi-year, multimillion dollar project. The temptation to approach the upgrade of the HPAL program in a piece meal fashion should be avoided. This is …

This invention is comprised of a transmission cable for carrying high current pulses in which an even numbered plurality of electrical conductors surrounds a central ground conductor. Each electrical conductor is connected so that it at any instant in time it will carry current of opposite polarity to the polarity carried by adjacent conductors. This arrangement cancels practically all of the external fields generated by current in the conductors.

The frequency of stress corrosion cracking in the near weld regions of the SRS reactor tank walls is apparently lower than the cracking frequency near the pipe-to-pipe welds in the primary cooling water system. The difference in cracking tendency can be attributed to differences in the welding processes, fabrication schedules, near weld residual stresses, exposure conditions and other system variables. This memorandum discusses the technical issues that may account the differences in cracking tendencies based on a review of the fabrication and operating histories of the reactor systems and the accepted understanding of factors that control stress corrosion cracking in austenitic stainless steels.

The invention consists of an improved method for the preparation of single phase, fine grained ceramic materials from precursor powder mixtures where at least one of the components of the mixture is an alkali earth carbonate. The process consists of heating the precursor powders in a partial vacuum under flowing oxygen and under conditions where the partial pressure of CO{sub 2} evolved during the calcination is kept to a very low level relative to the oxygen. The process has been found particularly suitable for the preparation of high temperature copper oxide superconducting materials such as YBa{sub 2}Cu{sub 3}O{sub x} ``123`` and YBa{sub 2}Cu{sub 4}O{sub 8} ``124``.

The objectives of this study are to determine the intrinsic kinetics and the product layer diffusion rate by minimizing the resistances to gas-phase pore diffusion, and eliminating complications due to pore filling. In the report, a grain model was used to introduce the various potentially rate-limiting processes. It was compared with results obtained with a distributed pore model by Bhatia & Perlmutter (1981). Comparing the predicted behavior of the surface areas with conversion, it was even possible to compare experimental results with other models. The conclusion of this study was that, even thought the kinetic parameters obtained with different samples differed much more if product layer diffusion assumed rate-limiting rather than the surface reaction, the shape of the predicted curve approached the experimental findings so much better, that product layer diffusion is indeed most likely to be rate-limiting. (VC)

Based on results of testing eight solids removal technologies and one pretreatment option, it is recommended that a centrifugal ultrafilter and polymeric ultrafilter undergo further testing as possible alternatives to the Norton Ceramic filters. Deep bed filtration should be considered as a third alternative, if a backwashable cartridge filter is shown to be inefficient in separate testing.

Newsletter of the Texas Bureau of Disease Control and Epidemiology discussing the news, activities, and events of the organization and other information related to health in Texas.

Kapton HN properties and the properties of the slip additive calcium phosphate dibasic (CaHPO{sub 4}) were investigated. Impurity analyses were performed on the compound by inductively coupled plasma (ICP) and ion chromatography (IC). Other analyses on the slip additive included: processing solution -- dissolution analysis, high-explosive compatibility studies, scanning electron microscopy/energy dispersive spectroscopy (SEM/EDS), and particle size distribution. Testing and analyses were also performed on Kapton HN film and other polyimide films that could serve as possible replacements for Kapton HN. The polyimide films that were tested are: Upilex-R, Upilex-S, Upilex-SGA, and Apical. The analyses performed were: infrared (IR), x-ray photoelectron spectroscopy (XPS), SEM/EDS, high-potential breakdown testing, (PVD) physical vapor deposition adhesion tests, and peel tests. Upilex-S flyer cables were also fabricated and successfully test fired. In addition to these raw material tests, production cables were chemically treated and destructively (high potential) tested. A long-term aging environment for production cables was also selected, and aging tests were begun. 9 figs., 7 tabs.

This report contains highlights on activities conducted at Y-12 Development Division for the period ending January 1, 1990. Ozone treatment removes trace amounts of organics and chloride ions from recycled acid. Heating significantly reduces this reaction time for removing these impurities. A new heater design was reinstalled on the recycle system, reducing the ozonation time from 70 to 100 hours to 30 to 40 hours. This reduction in ozonation time resulted in increased acid recovery and reduced acid wastes that had to be discarded. Shallow land burial in Bear Creek Burial Ground (BCBG) of depleted uranium and uranium alloy chips has been discontinued, and these materials will now be processed at the Uranium Chip Oxidation Facility (UCOF). A series of chip burns was made to reduce the overall flameout frequency to 1% to comply with UCOF safety documentation. This testing phase reduced the flameout frequency to 2 per 2,959 burns (<0.1%), which is a 92% decrease of flameouts over last quarter. This work successfully demonstrated that all of the uranium and uranium alloy chips (except sawfines) can be safely oxidized at UCOF with a flameout frequency of 1% or less. 2 refs., 3 figs., 1 tab.

The objective of this training is to: describe the responsibilities, resources, and goals of the Emergency Operations Center and be able to evaluate and interpret this information to best direct and allocate emergency, plant, and other resources to protect life and the Paducah Gaseous Diffusion Plant.

This report is a complete user's manual for KDYNA, the Earth Sciences version of DYNA2D. Because most features of DYNA2D have been retained in KDYNA much of this manual is identical to the DYNA2D user's manual.

This report highlights activities, events, and analyses of interest to public and private sector organizations associated with the natural gas industry. Volume and price data are presented each month for natural gas production, distribution, consumption, and interstate pipeline activities. Producer-related activities and underground storage data are also reported. 7 figs., 34 tabs.

Data presented in this PSM describe the supply and disposition of petroleum products in the United States and major US geographic regions. The data series describe production, imports and exports, inter-Petroleum Administration for Defense (PAD) District movements, and inventories by the primary suppliers of petroleum products in the United States (50 States and the District of Columbia). The reporting universe includes those petroleum sectors in Primary Supply. Included are: petroleum refiners, motor gasoline blenders, operators of natural gas processing plants and fractionators, inter-PAD transporters, importers, and major inventory holders of petroleum products and crude oil. When aggregated, the data reported by these sectors approximately represent the consumption of petroleum products in the United States. 12 figs., 46 tabs.

Three main issues giving purpose to our visit to CERN, ESRF and DESY were to: assess the current thinking at CERN on whether Eta, the gas desorption coefficient, would continue to decrease with continued with continued beam cleaning, determine if the time between NEG reconditioning could be expanded, and acquire a knowledge of the basic fabrication processes and techniques for producing beam vacuum chambers of copper.

As a consequence of the Chernobyl accident, data have been obtained throughout the Northern Hemisphere on the concentrations of radionuclides in air, vegetation, soil, water, and foodstuffs that could be important means of human exposure. At the IAEA's invitation, the traveler reviewed recently published data and handbook summaries. The traveler evaluated the need for revising the default values recommended in Chapter 5, Terrestrial and Aquatic Food Chain Transport,'' of IAEA Safety Series No. 57. All attempts at revision were made to keep the mathematical complexity of the models to a minimum without substantial underestimation of dose to critical population subgroups. The traveler also served as chairman of the Multiple Pathways Working Group of the Coordinated Research Program on VAMP. This group has been established to test predictions of models assessing multiple exposure pathways potentially leading to human exposure to {sup 137}Cs. Testing is carried out for major components of assessment models that predict deposition, environmental transport, food chain bioaccumulation, and subsequent uptake and retention in the human body and dose due to exposure to external gamma radiation.

Tritium was released to the atmosphere from the Savannah River Plant during an incident on September 2 and 3, 1984 between 10 PM and 3 AM. During this five hour period, 43,800 Ci of tritium, principally in the form of the oxide (HTO), was released. An additional 14,000, Ci was released during subsequent cleanup operations between September 3 and 7. The total amount released from the incident was 57,800 Ci. The HTO cloud initially moved northward and passed near the towns of New Ellenton and Aiken, SC. Two hours after the release began, the wind shifted and carried the cloud toward Columbia, SC. The cloud moved northeast during the daytime on September 3 over the east-central portion of North Carolina. Environmental sampling teams were dispatched by SRL, SRP, and SCDHEC (South Carolina Department of Health and Environmental Control). SRL collected air and vegetation samples and SRP collected vegetation, water, milk and bioassay samples. SCDHEC collected vegetation, milk, and water samples. The highest activity of HTO measured in vegetation was 501 pCi/mL onsite, 2522 pCi/mL at the plant boundary, and 9859 pCi/mL offsite. These concentrations were approximately 100 times larger than normal values. 13 refs., 7 figs., 10 tabs.

The general objective of this project is the investigation of phase equilibria for complex fluids using a novel methodology, Monte Carlo simulation in the Gibbs ensemble. The methodology enables the direct determination of the properties of two coexisting fluid phases (e.g. a liquid at equilibrium with its vapor) from a single computer experiment, and is applicable to multicomponent systems with arbitrary equilibrium constraints imposed. The specific goals of this work are to adapt the Gibbs technique to (a) highly asymmetric mixtures with large differences in size and potential energies of interaction (b) chain molecules and (c) ionic systems. Significant progress has been made in all three areas. In this paper, we will briefly describe the progress made in each area, using the same numbering scheme for the tasks as in the original proposal.

The use of a 1-kg solid-lithium x-ray and debris shield around each fusion fuel pellet prevents vaporization of, and destructive shock waves in, the Cascade blanket granules thereby increasing their lifetime. The shield vaporizes as it absorbs energy and the vapor flows into the blanket several centimeters. The shield also increases tritium breeding and enhances vacuum pumping of high Z materials that are vaporized in the fuel pellet. Using heavy ion beams allows illumination of the fuel pellets with the restricted geometry present in Cascade. We used a 5 MJ driver with 18 beams (one 3 {times} 3 array from each end).

This report presents the status at the end of 1989 and the outlook for commercial nuclear capacity and generation for all countries in the world with free market economies (FME). The report provides documentation of the US nuclear capacity and generation projections through 2030. The long-term projections of US nuclear capacity and generation are provided to the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) for use in estimating nuclear waste fund revenues and to aid in planning the disposal of nuclear waste. These projections also support the Energy Information Administration's annual report, Domestic Uranium Mining and Milling Industry: Viability Assessment, and are provided to the Organization for Economic Cooperation and Development. The foreign nuclear capacity projections are used by the DOE uranium enrichment program in assessing potential markets for future enrichment contracts. The two major sections of this report discuss US and foreign commercial nuclear power. The US section (Chapters 2 and 3) deals with (1) the status of nuclear power as of the end of 1989; (2) projections of nuclear capacity and generation at 5-year intervals from 1990 through 2030; and (3) a discussion of institutional and technical issues that affect nuclear power. The …