This report documents the procedures used to convert archaeological data for the INEL to digital format, lists the equipment used, and explains the verification and validation steps taken to check data entry. It also details the production of an engineered interface between ARC/INFO and Oracle.

This project is a major step in the Department of Energy`s program to show that ultra-clean coal-water slurry fuel (CWF) can be produced from selected coals and that this premium fuel will be a cost-effective replacement for oil and natural gas now fueling some of the industrial and utility boilers in the United States. The replacement of oil and gas with CWF can only be realized if retrofit costs are kept to a minimum and retrofit boiler emissions meet national goals for clean air. These concerns establish the specifications for maximum ash and sulfur levels and combustion properties of the CWF. This cost-share contract is a 48-month program which started on September 30, 1992. This report discusses the technical progress made during the 4th quarter of the project from July 1 to September 30, 1993.

The Federal government's high-level waste disposal program is designed to build a permanent repository for highly radioactive waste from nuclear power plants and defense facilities. The Nuclear Waste Policy Act of 1982 (NWPA) created an office in the Department of Energy (DOE) to develop this repository, to be paid for by a fee on nuclear-generated electricity.

This report discusses the issues of the U.S.-Japanese trade relations of the Reagan and Bush Administrations, and the Clinton Administration.

Low absorption coatings were examined using a high repetition rate copper vapor laser to study the surface temperature as a function power. Nonlinear absorption was observed in some of the coatings as a result of increased incident power. A variety of commercial coating vendors using common dielectric oxide material combinations were surveyed. Wavelength, coating material, and coating vendor were varied to study their affects on the linearity of the absorption. The films were deposited by electron beam or ion beam sputtering technologies. Changes in the film characteristics were observed after exposure to high incident power. The nature of these changes and their permanency were also examined.

The purpose of this program is to determine the centers of the high-energy linac (HEL) BPMs using beam information, and to compare this information with the existing surveying information. It measures directly and quantitatively the amount of quad steering in each of the HEL quads. It is hoped that this program is all that is needed to make this measurement This procedure is based on the observation of the beam position in a BPM downstream of a quad while changing the magnetic field in that quad. If the beam is centered in the quad, then this change will have no effect on the trajectory of the beam. However, if the beam is off center at the quad, changing the field will steer the beam. This measurement therefore can be used to measure the position of the beam in the quad under examination.

In the framework of relativistic nuclear field theory the authors discuss and compare the different approaches in the treatment of nuclear-many-problem with inclusion of two-body correlations. The equations are solved self-consistently in the full Dirac space, so avoiding the ambiguities in the choice of the effective scattering amplitude. The results are compared with the standard method, where one only determines the scattering amplitude for positive energy spinors. Furthermore they tested the assumption of momentum independent self-energy. The results for asymmetric matter are in the structure similar to the outcome of the relativistic Hartree-Fock approximation, but differ from the nonrelativistic treatment. The agreement with the empirical values is quite satisfactory.

The Waste Contaminants at Military Bases Working Group has screened six prospective demonstration projects for consideration by the Federal Advisory Committee to Develop On-Site Innovative Technologies (DOIT). These projects include the Kirtland Air Force Base Demonstration Project, the March Air Force Base Demonstration Project, the McClellan Air Force Base Demonstration Project, the Williams Air Force Base Demonstration Project, and two demonstration projects under the Air Force Center for Environmental Excellence. A seventh project (Port Hueneme Naval Construction Battalion Center) was added to list of prospective demonstrations after the September 1993 Working Group Meeting. This demonstration project has not been screened by the working group. Two additional Air Force remediation programs are also under consideration and are described in Section 6 of this document. The following information on prospective demonstrations was collected by the Waste Contaminants at Military Bases Working Group to assist the DOIT Committee in making Phase 1 Demonstration Project recommendations. The remainder of this report is organized into seven sections: Work Group Charter`s mission and vision; contamination problems, current technology limitations, and institutional and regulatory barriers to technology development and commercialization, and work force issues; screening process for initial Phase 1 demonstration technologies and sites; demonstration descriptions -- …

The Winter Fuels Report is intended to provide concise, timely information to the industry, the press, policymakers, consumers, analysts, and State and local governments on the following topics: distillate fuel oil net production, imports and stocks on a US level and for all Petroleum Administration for Defense Districts (PADD) and product supplied on a US level; propane net production, imports and stocks on a US level and for PADD`s I, II, and III; natural gas supply and disposition and underground storage for the US and consumption for all PADD`s; as well as selected National average prices. Residential and wholesale pricing data for heating oil and propane for those States participating in the joint Energy Information Administration (EIA)/State Heating Oil and Propane Program; crude oil and petroleum price comparisons for the US and selected cities; and a 6--10 Day, and 90-Day outlook for temperature and precipitation and US total heating degree-days by city.

Radioactive operations in the Defense Waste Processing Facility (DWPF) will require that the Savannah River Technology Center (SRTC) perform analyses and special studies with actual Savannah River Site (SRS) high-level waste sludge. SRS Tank 42 and Tank 51 will comprise the first batch of sludge to be processed in the DWPF. Approximately 25 liters of sludge from each of these tanks will be characterized and processed in the Shielded Cells of SRTC. During the campaign, processes will include sludge characterization, sludge washing, rheology determination, mixing, hydrogen evolution, feed preparation, and vitrification of the waste. To complete the campaign, the glass will be characterized to determine its durability and crystallinity. This document describes the types of samples that will be produced, the sampling schedule and analyses required, and the methods for sample and analytical control.

In the process of developing a design for the design report, many side questions or comments arose which were not completely answered or investigated because the work was outside the scope of developing a base design. I have pored over my meeting notes and tried to list all such chimney 'open issues' in this engineering note.

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In the process of developing a design for the design report, side questions or comments arose which were not completely answered or investigated because the work was outside the scope of developing a base design. I have pored over my meeting notes and tried to list all such control dewar 'open issues' in this engineering note.

This engineering note provides background information regarding the control dewar secondary vacuum container. The secondary vacuum container has it's origin with the CDP control dewar design. The name secondary vacuum container replaced the CDP term 'Watt can' which was named after Bob Watt (SLAC), a PAC/DOE review committee member who participated in a review of CDP and recommended a secondary vacuum enclosure. One of the most fragile parts of the control dewar design is the ceramic electrical feed throughs located in the secondary vacuum container. The secondary vacuum container is provided to guard against potential leaks in these ceramic insulating feed throughs. The secondary vacuum container has a pumping line separate from the main solenoid/control dewar insulating vacuum. This pumping line is connected to the inlet of the turbo pump for initial pumpdown. Under normal operation the container is isolated. Should a feedthrough develop a small leak, alternate pumping arrangements for the secondary vacuum container could be arranged. The pressure in the secondary vacuum container should be kept in a range that the breakdown voltage is kept at a maximum. The breakdown voltage is known to be a function of pressure and is described by a Paschen curve. I cannot …

The calculations done to size the control dewar subcooler were done to obtain a sufficient subcooler size based on some conservative assumptions. The final subcooler design proposed in the design report will work even better because (1) It has more tubing length, and (2) will have already subcooled liquid at the inlet due to the transfer line design. The subcooler design described in the 'Design Report of the 2 Tesla Superconducting Solenoid for the Fermilab D0 Detector Upgrade' is the final design proposed. A short description of this design follows. The subcooler is constructed of 0.50-inch OD copper tubing with 1.0-inch diameter fins. It has ten and one half spirals at a 11.375-inch centerline diameter to provide 31 feet of tubing length. The liquid helium supply for the solenoid flows through the subcooler and then is expanded through a J-T valve. The subcooler spirals are immersed in the return two phase helium process stream. The return stream is directed over the finned tubing by an annulus created by a 10-inch pipe inside a 12-inch pipe. The transfer line from the refrigerator to the control dewar is constructed such that the liquid helium supply tube is in the refrigerator return stream, …

This engineering note documents information gathered and design decisions made regarding the vapor cooled current leads for the D-Zero Solenoid. The decision was made during design group meetings that the D-Zero Solenoid, rated at 4825 amps, should use vapor cooled current leads rated at 6000 amps. CDF uses 6000 amp leads from American Magnetics Inc. (AMI) and has two spares in their storage lockers. Because of the spares situation and AMI's reputation, AMI would be the natural choice of vendor. The manufacturer's listed helium consumption is 19.2 liters/hr. From experience with these types of leads, more stable operation is acheived at an increased gas flow. See attached E-Mail message from RLS. We have decided to list the design flow rate at 28.8 liquid liters/hr in the design report. This corresponds to COFs operating point. A question was raised regarding how long the current leads could last at full current should the vapor cooling flow was stopped. This issue was discussed with Scott Smith from AMI. We do not feel that there is a problem for this failure scenario.

New corrosion coupons were installed in the Feed Preparation System and the Melter/Off-Gas System of Integrated DWPF Melter System (IDMS) in August 1993. The new coupons are replacements for similar coupons which were in the IDMS since 1989 but were removed for metallurgical evaluation in April 1993. original coupons still remain on the corrosion racks in the Melter and the Off-Gas Stack. Baseline data for the replacement coupons are described in this report.

Summary of Batch Extraction Experiments: (1) Resin extraction rate is not significantly affected by agitation intensity and low agitation should be suitable for the continuous extraction process; (2) The effect of resin particle size on the extraction rate and yield is obvious. Because of the fine size of the composite resin concentrate (80% minus 200 mesh), the extraction reaction occurs in reasonable times and process design conditions can be established accordingly; (3) The effect of temperature on the rate and yield of the extraction process is found to be very significant. Higher temperatures (about 60{degree}C) should be considered for the continuous extraction circuit; (4) The effect of solids concentration on the extraction rate is moderate. As concluded from our characterization study, it is known that fossil resin is mainly composed of aliphatic components, partially aromatized multicyclic compounds with a small number of oxygen functional groups. The solvent, heptane, is also a nonpolar aliphatic compound. It is expected that no chemical reaction will occur in such an extraction process at low temperature (0--90{degree}C). The main interaction between resin and heptane is expected to be the van-der-Waals-forces of interaction associated with solvation phenomena. In this regard, the resin extraction rate should be …

The final report for the research in the area of `Sensitivity in Risk Assessment for the Yucca Mountain High-Level Nuclear Waste Repository Site: The Model and the Data` includes the following contributions: A. Articles (1) Ho, C.-H. 1993. Time Regimes in the Volcanic History of Vesuvius: 1631-1944, Bulletin of Volcanology. (2) Ho, C.-H. 1993. Sensitivity in Risk Assessment for the Yucca Mountain High-Level Nuclear Waste Repository Site: The Model and the Data. B. Paper presented, `Comments on the Preliminary Draft of Los Alamos National Laboratory on the Status of Volcanic Hazard Studies for the Yucca Mountain Site Characterization Project`, presented at the meeting of DOE-NRC Technical Exchange on Volcanism Studies held in Las Vegas on June 9, 1993.

This report summarizes the activities and progress by ICF Kaiser Engineers conducted on behalf of Los Alamos National Laboratories (LANL) for the US Department of Energy, Office of Waste Management (EM-33) in the area of improving methods for Cost Estimation. This work was conducted between October 1, 1992 and September 30, 1993. ICF Kaiser Engineers supported LANL in providing the Office of Waste Management with planning and document preparation services for a Cost and Schedule Estimating Guide (Guide). The intent of the Guide was to use Activity-Based Cost (ABC) estimation as a basic method in preparing cost estimates for DOE planning and budgeting documents, including Activity Data Sheets (ADSs), which form the basis for the Five Year Plan document. Prior to the initiation of the present contract with LANL, ICF Kaiser Engineers was tasked to initiate planning efforts directed toward a Guide. This work, accomplished from June to September, 1992, included visits to eight DOE field offices and consultation with DOE Headquarters staff to determine the need for a Guide, the desired contents of a Guide, and the types of ABC estimation methods and documentation requirements that would be compatible with current or potential practices and expertise in existence at …

The primary objective of this task is to evaluate the proposed design modifications to the sample system, including the adequacy of the recommended eductor and the quality of samples obtained from the modified system. Presently, the sample streams are circulated from the originating tank, through a Hydragard{trademark} sampler system, and back to the originating tank. The overflow from the Hydragard{trademark} sampler flows to the Recycle Collection Tank (RCT). This report outlines the planned quality assurance controls for the design modification task, including organization and personnel, surveillances, and records package.

Newsletter of the Texas Department of Health discussing the news, activities, and events of the organization and other information related to health in Texas.

In the third quarterly report adsorption of heavy metals ions such as Cu(II) and Cr(VI) onto soils drawn from the laboratory-type wetland was shown to be weak. Secondly, it was shown that modified-clays did adsorb Cr(VI) ions strongly at pH 4.5. Further, studies on the pH dependence of the adsorption of {beta}-naphthoic acid, (NA), a well-documented contaminant in many oil and gas well waste waters onto modified-clays were undertaken and it was shown that uptake of NA by modified-clays was of the high affinity type at pH 4.5 and 7.0, but weak at pH 9.0. Adsorption of heavy metal ions, Cu{sup 2+}, and Cr(VI) onto algae, a proposed wetland amendment, was carried out and the results were presented and discussed in the fourth quarterly report. Uptake of NA by the soil component of the laboratory-type wetland was monitored as a function of pH. This quarterly report presents results from studies on the uptake of phenol and {beta}-naphthoic acid by laboratory-type wetlands designed and built during the earlier phases of this study. The uptake of phenol by the wetlands is quite rapid, and nearly complete in 50 hours, but it was also found that evaporative losses of phenol from the supernatant …

The Committee`s evaluation of vanadium alloys as a structural material for fusion reactors was constrained by limited data and time. The design of the International Thermonuclear Experimental Reactor is still in the concept stage, so meaningful design requirements were not available. The data on the effect of environment and irradiation on vanadium alloys were sparse, and interpolation of these data were made to select the V-5Cr-5Ti alloy. With an aggressive, fully funded program it is possible to qualify a vanadium alloy as the principal structural material for the ITER blanket in the available 5 to 8-year window. However, the data base for V-5Cr-5Ti is United and will require an extensive development and test program. Because of the chemical reactivity of vanadium the alloy will be less tolerant of system failures, accidents, and off-normal events than most other candidate blanket structural materials and will require more careful handling during fabrication of hardware. Because of the cost of the material more stringent requirements on processes, and minimal historical worlding experience, it will cost an order of magnitude to qualify a vanadium alloy for ITER blanket structures than other candidate materials. The use of vanadium is difficult and uncertain; therefore, other options should …