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.

The purpose of this note is to document an estimate of beam loss in the RHIC facility which is required for analysis of a variety of issues related to radiation safety.

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.

The Second International Workshop on Human Chromosome 19 was hosted on January 25 and 26, 1992, by the Department of Human Genetics, University Hospital Nijmegen, The Netherlands, at the `Meerdal Conference Center`. The workshop was supported by a grant from the European Community obtained through HUGO, the Dutch Research Organization (NWO) and the Muscular Dystrophy Association (MDA). Travel support for American participants was provided by the Department of Energy. The goals of this workshop were to produce genetic, physical and integrated maps of chromosome 19, to identify inconsistencies and gaps, and to discuss and exchange resources and techniques available for the completion of these maps. The second day of the meeting was largely devoted to region or disease specific efforts. In particular, the meeting served as a platform for assessing and discussing the recent progress made into the molecular elucidation of myotonic dystrophy.

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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.

The complete CombiNO[sub x], process has now been demonstrated at a level that is believed to be representative of a full-scale boiler in terms of mixing capabilities. A summary of the results is displayedin Figure 5-1. While firing Illinois Coal on the Reburn Tower, Advanced Reburning was capable of reducing NO[sub x], by 83 percent. The injection of methanol oxidized 50--58 percent of the existing NO to N0[sub 2]. Assuming that 85 percent of the newly formed N0[sub 2] can be scrubbed in a liquor modified wet-limestone scrubber, the CombiNO[sub x], process has been shown capable of reducing NO[sub 2], by 90--91 percent in a large pilot-scale coal-fired furnace. There is still uncertainty regarding the fate of the N0[sub 2] formed with methanol injection. Tests should be conducted to determine whether the reconversion is thermodynamic or catalytic, and what steps can be taken (such as quench rate) to prevent it from happening.

The complete CombiNO{sub x}, process has now been demonstrated at a level that is believed to be representative of a full-scale boiler in terms of mixing capabilities. A summary of the results is displayed in Figure 5-1. While firing Illinois Coal on the Reburn Tower, Advanced Reburning was capable of reducing NO{sub x}, by 83 percent. The injection of methanol oxidized 50--58 percent of the existing NO to N0{sub 2}. Assuming that 85 percent of the newly formed N0{sub 2} can be scrubbed in a liquor modified wet-limestone scrubber, the CombiNO{sub x}, process has been shown capable of reducing NO{sub 2}, by 90--91 percent in a large pilot-scale coal-fired furnace. There is still uncertainty regarding the fate of the N0{sub 2} formed with methanol injection. Tests should be conducted to determine whether the reconversion is thermodynamic or catalytic, and what steps can be taken (such as quench rate) to prevent it from happening.

Amax R D will perform laboratory scale development of a promising, practical catalyst for the selective oxidation of methane to methanol. The primary component of this catalyst is vanadium-phosphate (VPO) which has shown good activity and selectivity in the partial oxidation of n-butane and propane but has not been studied in detail for methane oxidation. The goal of the project is to develop a catalyst which allows methane oxidation to methanol to be conducted at high conversion and selectivity. A low CH[sub 4]/O[sub 2] ratio will be employed with air as the source of oxygen. Temperatures below 600[degrees]C and pressures up to 20 atm are to be investigated. The use of steam in the feed gas will also be investigated. The catalyst development strategy will be to utilize promoters and supports to improve the activity and selectivity of the unmodified VPO catalyst. The catalyst testing reactor system was used to perform blank (empty) reactor runs over a wide range of temperatures, pressure, and flow rates. No methane conversion was observed at temperatures of 500[degrees]C or lower in any of the tests. At higher temperatures, significant methane conversion to carbon dioxide was observed. At 550[degrees]C, 300 psig, and the highest flow …

Amax R&D will perform laboratory scale development of a promising, practical catalyst for the selective oxidation of methane to methanol. The primary component of this catalyst is vanadium-phosphate (VPO) which has shown good activity and selectivity in the partial oxidation of n-butane and propane but has not been studied in detail for methane oxidation. The goal of the project is to develop a catalyst which allows methane oxidation to methanol to be conducted at high conversion and selectivity. A low CH{sub 4}/O{sub 2} ratio will be employed with air as the source of oxygen. Temperatures below 600{degrees}C and pressures up to 20 atm are to be investigated. The use of steam in the feed gas will also be investigated. The catalyst development strategy will be to utilize promoters and supports to improve the activity and selectivity of the unmodified VPO catalyst. The catalyst testing reactor system was used to perform blank (empty) reactor runs over a wide range of temperatures, pressure, and flow rates. No methane conversion was observed at temperatures of 500{degrees}C or lower in any of the tests. At higher temperatures, significant methane conversion to carbon dioxide was observed. At 550{degrees}C, 300 psig, and the highest flow rate …

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.

The 200 West Area Carbon Tetrachloride Expedited Response Action (ERA) is being conducted by the US Department of Energy (DOE) at the direction of the US Environmental Protection Agency (EPA) and the Washington Department of Ecology as a provision of both the Comprehensive Environmental Response Compensation and Liability Act of 1980 (CERCLA) and the Integrated Demonstration for Cleanup of Volatile Organic Compounds at Arid Sites (VOC-Arid ID). The ERA allows expedited response to be taken at waste sites where damage to the environment can be significantly reduced by early action to locate, identify the extent, and remediate imminent hazards. The ERA is focusing specifically on the removal of carbon tetrachloride vapor from the soil column and protection of the groundwater in the 200 West Area. The VOC-Arid ID program allows demonstration of new drilling technologies for environmental characterization monitoring and remediation. Soil vapor vacuum extraction has been proposed to remediate the site. This may require vapor extraction wells to be installed within the plume.

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 results for the control run for a single particle are shown in Figure 1. The figure, which includes other thermolytic data for Illinois No. 6 coal, shows that the particle was stable in size to around 440[degree]C. At that point it contracted very rapidly to about half its size over the next 15[degrees]. Also shown are data for the same coal from SRI's field ionization mass spectrometer (FIMS), in which case a sample of the coal is heated at 2.5[degrees]C/min from ambient to 500[degrees]C and the effluent is swept into mass spectrometer. The evolution of the coal volatiles is reflected by accumulated ion count with increasing temperature, and is presented in the figure as the fraction of total volatiles. As the figure shows, the abrupt increase in volatility corresponds very closely to the equally abrupt reduction in particle size. The weight average molecular weight profile from the FIMS work is also in the figure, and shows that the coal experiences a simple loss of volatiles of increasing molecular weight up to around 440[degrees]C. At that point pyrolysis and fragmentation come about, reflected in the quick reversal and decline in molecular weight. The high rate of volatility and shrinkage are …

The results for the control run for a single particle are shown in Figure 1. The figure, which includes other thermolytic data for Illinois No. 6 coal, shows that the particle was stable in size to around 440{degree}C. At that point it contracted very rapidly to about half its size over the next 15{degrees}. Also shown are data for the same coal from SRI`s field ionization mass spectrometer (FIMS), in which case a sample of the coal is heated at 2.5{degrees}C/min from ambient to 500{degrees}C and the effluent is swept into mass spectrometer. The evolution of the coal volatiles is reflected by accumulated ion count with increasing temperature, and is presented in the figure as the fraction of total volatiles. As the figure shows, the abrupt increase in volatility corresponds very closely to the equally abrupt reduction in particle size. The weight average molecular weight profile from the FIMS work is also in the figure, and shows that the coal experiences a simple loss of volatiles of increasing molecular weight up to around 440{degrees}C. At that point pyrolysis and fragmentation come about, reflected in the quick reversal and decline in molecular weight. The high rate of volatility and shrinkage are …

Figures 3, 4, and 5 display images of two adjacent particles chosen for analysis with characteristic dimensions of 50--100 {mu}m Figure 3 shows that there is essentially no change up to 395{degrees}C over an 18 min period, but at that point the particle labeled a begins to shrink. The action continues in Figure 4 where the particle contracts to about half its initial size over a 45 sec period as the temperature, increases from 424{degrees}C to 430{degrees}C, at which point the contraction stops. The size profile for a is presented in Figure 6 and compares very well with the profile generated in an earlier experiment from our last report. As just noted, this agreement suggests that this behavior is representative of at least one class of particle in the sample. Figure 5 shows that there is a second, higher temperature range of activity, represented by the changes in particle b. This particle contracts to about half its size from 450{degrees} to 460{degrees}C over 1 min. The temperature was held at 460{degrees} and there appears to be an additional 7--10% contraction over 10 min at that temperature, although the scatter seen in Figure 6 shows that change is not outside our …

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 …

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.

Genetic mapping is approached using the techniques of high resolution fluorescence in situ hybridization (FISH). This technology and the results of its application are designed to rapidly generate whole genome as tool box of expressed sequence to speed the identification of human disease genes. The results of this study are intended to dovetail with and to link the results of existing technologies for creating backbone YAC and genetic maps. In the first eight months, this approach generated 60--80% of the expressed sequence map, the remainder expected to be derived through more long-term, labor-intensive, regional chromosomal gene searches or sequencing. The laboratory has made significant progress in the set-up phase, in mapping fetal and adult brain and other cDNAs, in testing a model system for directly linking genetic and physical maps using FISH with small fragments, in setting up a database, and in establishing the validity and throughput of the system.

Genetic mapping is approached using the techniques of high resolution fluorescence in situ hybridization (FISH). This technology and the results of its application are designed to rapidly generate whole genome as tool box of expressed sequence to speed the identification of human disease genes. The results of this study are intended to dovetail with and to link the results of existing technologies for creating backbone YAC and genetic maps. In the first eight months, this approach generated 60--80% of the expressed sequence map, the remainder expected to be derived through more long-term, labor-intensive, regional chromosomal gene searches or sequencing. The laboratory has made significant progress in the set-up phase, in mapping fetal and adult brain and other cDNAs, in testing a model system for directly linking genetic and physical maps using FISH with small fragments, in setting up a database, and in establishing the validity and throughput of the system.

The Oklahoma Geological Survey (OGS), the Geological Information Systems department, and the School of Petroleum and Geological Engineering at the University of Oklahoma have engaged in a program to identify and address Oklahoma`s oil recovery opportunities in fluvial-dominated deltaic (FDD) reservoirs. This program includes the systematic and comprehensive collection and evaluation of information on all of Oklahoma`s FDD reservoirs and the recovery technologies that have been (or could be) applied to those reservoirs with commercial success. This data collection and evaluation effort will be the foundation for an aggressive, multifaceted technology transfer program that is designed to support all of Oklahoma`s oil industry, with particular emphasis on smaller companies and independent operators in their attempts to maximize the economic producibility of FDD reservoirs. Specifically, this project will identify all FDD oil reservoirs in the State; group those reservoirs into plays that have similar depositional and subsequent geologic histories; collect, organize and analyze all available data; conduct characterization and simulation studies on selected reservoirs in each play; and implement a technology transfer program targeted to the operators of FDD reservoirs to sustain the life expectancy of existing wells with the ultimate objective of increasing oil recovery.