This report contains brief discussions on topics of high-pressure sciences, astrophysics, and geosciences. (LSP)

The U.N. Development Program (UNDP) coordinates and provides funding for most U.N. development assistance programs. In FY1994, the U.S. contribution of $116 million made the United States the largest donor, comprising about 12 percent of the agency's budget.

'The primary purpose of this report is to document a Defense-in-Depth (DID) accident analysis evaluation for Department of Energy (DOE) Savannah River Site (SRS) Tritium Facility Buildings 232-H, 233-H, and 234-H. The purpose of a DID evaluation is to provide a more realistic view of facility radiological risks to the offsite public than the bounding deterministic analysis documented in the Safety Analysis Report, which credits only Safety Class items in the offsite dose evaluation.'

This technical report defines and describes a Crystalline Beam. This is an ordered state of matter made of electrically charged ions which are moving together in a storage ring with very high density and small velocity spread. In particular, the paper analyses the requirements for the confinement and the stability of the Beam. It is demonstrated that a storage ring made of one circular weak-focusing magnet, similar to a Betatron, is the most suitable for the confinement and stability of the Crystalline Beam. The disruptive effects of drift insertions have also been investigated. Requirements on final densities and velocity spreads are also calculated and reported. A matrix formalism is developed for the design of the storage ring. The important issue of the disruption caused by the curvature of the closed trajectory is not here discussed; it is the subject of a subsequent paper.

This User`s Guide describes the installation and use of the Meta- Transport Library protocol base classes. This software package includes the full source code for the implementation, as well as man pages and appropriate documents. The fully built MTL is a C++ library file that is linked into derived protocol code.

The Xpress Transfer Protocol (XTP) is a transport layer protocol designed to provide a wide range of communication services built on the concept that orthogonal protocol mechanisms can be combined to produce appropriate paradigms within the same basic framework. Rather than using a separate protocol for each type of communication, XTP`s protocol options and control of the packet exchange patterns allow the application to create appropriate paradigms such as unreliable datagrams, unreliable arbitrarily long datagrams, reliable datagrams, transactions, unreliable streams, reliable connections, and many others. Error control, flow control, and rate control are each configured to the needs of the communication. SandiaXTP is an object oriented implementation of XTP 3.7. The core of base classes used in SandiaXTP come from the Meta-Transport Library software. The SandiaXTP implementation of XTP 3.7 is a user space daemon. User`s application code makes request of the daemon, and the daemon satisfies them. This User`s Guide describes the installation and use of the SandiaXTP object-oriented implementation of XTP 3.7. The software package includes the full source code for the implementation, as well as man pages and appropriate documents. The fully built SandiaXTP is a user-space daemon that implements XTP 3.7.

A panel of experts in the fields of process engineering, process chemistry, and safety analysis met together on January 26, 1993, and February 19, 1993, to discuss nuclear safety and nuclear criticality potential in the Defense Waste Processing Facility (DWPF) processes. Nuclear safety issues and possibilities of nuclear criticality incidents in the DWPF were examined in depth. The discussion started at the receipt of slurry feeds: The Low Point Pump Pit Precipitate Tank (LPPPPT) and the Low Point Pump Pit Sludge Tank (LPPPST), and went into detail the whole DWPF processes. This report provides discussion of each of the areas and processes of the DWPF in terms of potential nuclear safety issues and nuclear criticality concerns.

This technical report defines and describes a Crystalline Beam. This is an ordered state of matter made of electrically charged ions which are moving together in a storage ring with very high density and small velocity spread. In particular, the paper analyses the requirements for the confinement and the stability of the Beam. It is demonstrated that a storage ring made of one circular weak-focusing magnet, similar to a Betatron, is the most suitable for the confinement and stability of the Crystalline Beam. The disruptive effects of drift insertions have also been investigated. Requirements on final densities and velocity spreads are also calculated and reported. A matrix formalism is developed for the design of the storage ring. The important issue of the disruption caused by the curvature of the closed trajectory is not here discussed; it is the subject of a subsequent paper.

Subsection (b) of Public Law 101-510, Section 3137, {open_quotes}Safety Measures for Waste Tanks at Hanford Nuclear Reservation{close_quotes} (PL 101-510), requires the Secretary of Energy to {open_quotes}identify those tanks that may have a serious potential for release of high-level waste due to uncontrolled increase in temperature or pressure{close_quotes}. One of the tanks that has been identified to meet this criteria is single-shell tank (SST) 241-C-106 (Wilson and Reep 1991). This report presents the results of an evaluation of the safety issue associated with tank 241-C-106: the continued cooling required for high heat generation in tank 241-C-106. If tank 241-C-106 should start leaking, continued addition of water for cooling could possibly increase the amount of leakage to the soil column. In turn, if the current methods of cooling tank 241-C-106 are stopped, the sludge temperatures may exceed established temperature limits, the long term structural integrity of the tank liner and concrete would be jeopardized, leading to an unacceptable release to the environment. Among other conclusions, this evaluation has determined that tank 241-C-106 contains enough heat generating wastes to justify retaining this tank on the list {open_quotes}Single-Shell Tanks With High Heat Loads (>40,000 Btu/H){close_quotes} and that to confirm the structural integrity needed for …

Pacific Northwest Laboratory (PNL) is developing a borosilicate glass as a solid, stable medium for the disposal of high-level radioactive waste at the Hanford site. They are optimizing the glass forming region and developing process models to be used in the Hanford Waste Verification Project (HWVP). Their experimentally-based statistical approach for optimizing the glass composition for HWVP has been designated the Composition Variability Study (CVS). In Part 1 of the CVS study PNL tested wide ranges of composition developed first-order empirical models, and provided input for planning CVS-2. In part 2, they are generating glass property data for a number of compositions in order to develop second-order empirical models which will be used to identify the composition region that simultaneously satisfies all quality and processability requirements of HWVP.

No abstract currently available for this report as the present time.

Historically the Black Colleges and Universities wing of the US Department of Energy (DOE) provided funds to Claflin College, Orangeburg, S.C. to conduct a student Science Enrichment Training Program for a period of six weeks during 1990 summer. Fifty participants were selected from a pool of 130 applicants, generated by the High School Seniors and Juniors and the Freshmen class of 1989--90 at Claflin College. The program primarily focused on high ability students, with potential for Science, Mathematics and Engineering Careers. The major objectives of the program were (1) to increase the pool of well qualified college-entering minority students who will elect to go in Physical Science and Engineering and (2) to increase the enrollment in Chemistry and Preprofessional -- Pre-Med, Pre-Dent. etc -- majors at Claflin College by including the Claflin students to participate in summer academic program. The summer academic program consisted of Chemistry and Computer Science training. The program placed emphasis upon laboratory experience and research. Visits to Scientific and Industrial laboratories were arranged. Guest speakers drawn from academia, industry and several federal agencies, addressed the participants on the future role of Science in the industrial growth of United States of America. The guest speakers also acted …

The electron beam technology demonstration at SRS has potential benefit to some groundwater remediation projects at SR and other DOE facilities. At SRS, organic contaminants are the most commonly found contaminants in groundwaters, consequently, this technology has the potential to remove the contaminants fro the groundwaters effectively. The primary objective is to provide site-specific data to support SRS remediation actions. The secondary objective for the technology demonstration will be to obtain necessary information for a full-scale remediation treatment system. The information will include operating and construction costs, removal efficiency, potential operating problems, and process chemical dosages if applied.

Pacific Northwest Laboratory (PNL) is developing a borosilicate glass as a solid, stable medium for the disposal of high-level radioactive waste at the Hanford site. They are optimizing the glass forming region and developing process models to be used in the Hanford Waste Verification Project (HWVP). Their experimentally-based statistical approach for optimizing the glass composition for HWVP has been designated the Composition Variability Study (CVS). In Part 1 of the CVS study PNL tested wide ranges of composition developed first-order empirical models, and provided input for planning CVS-2. In part 2, they are generating glass property data for a number of compositions in order to develop second-order empirical models which will be used to identify the composition region that simultaneously satisfies all quality and processability requirements of HWVP.

On August 11, 1990 during an ornithological survey at the True/Mid Pacific Geothermal Venture proposed well site No.2, a Hawaiian hawk (Buteo solitarius) nest with a nestling was found approximately 430 feet from the proposed well pad clearing. The US Fish and Wildlife Service and the State of Hawaii have listed the Hawaiian hawk as an endangered species. Future development in this area could be impacted by the presence of this endangered avian species and its nest in such close proximity to the proposed well site. This report summarizes the results of observations at the nest on May 3, 1991.

'The Savannah River Technology Center (SRTC) has participated in a round robin testing program which was conducted under the auspices of the Department of Energy''s (DOE) Tanks Focus Area (TFA) for Immobilization.'

'The waste glass produced in the SRS Defense Waste Processing Faiclity (DWPF) process must comply with Waste Acceptance Product Specifications (WAPS) and process control requirements by demonstrating, to a high degree of confidence, that melter feed will produce glass satisfying all quality and processing requirements.'

Using ORNL information on the characterization of the tank waste sludges, SRTC performed extensive bench-scale vitrification studies using simulants. Several glass systems were tested to ensure the optimum glass composition (based on the glass liquidus temperature, viscosity and durability) is determined. This optimum composition will balance waste loading, melt temperature, waste form performance and disposal requirements. By optimizing the glass composition, a cost savings can be realized during vitrification of the waste. The preferred glass formulation was selected from the bench-scale studies and recommended to ORNL for further testing with samples of actual OR waste tank sludges.

'The primary purpose of this report is to document a Defense-in-Depth (DID) accident analysis evaluation for Department of Energy (DOE) Savannah River Site (SRS) Tritium Facility Buildings 232-H, 233-H, and 234-H. The purpose of a DID evaluation is to provide a more realistic view of facility radiological risks to the offsite public than the bounding deterministic analysis documented in the Safety Analysis Report, which credits only Safety Class items in the offsite dose evaluation.'

Tank C-111 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Results presented here represent the best available data on the headspace constituents of Tank C-111. Almost all of the data in this report was obtained from samples collected on September 13, 1994.Data from 2 other sets of samples, collected on August 10, 1993 and June 20, 1994, are in generally good agreement with the more recent data. The tank headspace temperature was determined to be 27 C. Air from the Tank C-111 headspace was withdrawn via a 7.9 m-long heated sampling probe mounted in riser 6, and transferred via heated tubing to the VSS sampling manifold. All heated zones of the VSS were maintained at approximately 50 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, Pacific Northwest Laboratories, and Oregon Graduate Institute of Science and Technology through a contract with Sandia National Laboratories. The 39 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 14 trip blanks provided by the laboratories. Tank C-111 …

Tank C-112 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Tank C-112 is a single-shell tank which received first-cycle decontamination waste from B Plant and was later used as a settling tank. Samples were collected from Tank C-112 using the vapor sampling system (VSS) on August 11, 1994 by WHC Sampling and Mobile Laboratories. The tank headspace temperature was determined to be 28 C. Air from the Tank C-112 headspace was withdrawn via a 7.9 m-long heated sampling probe mounted in riser 4, and transferred via heated tubing to the VSS sampling manifold. All heated zones of the VSS were maintained at approximately 50 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, Pacific Northwest Laboratories, and Oregon Graduate Institute of Science and Technology through a contract with Sandia National Laboratories. The 39 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 14 trip blanks and 2 field blanks provided by the laboratories.

Tank BY-105 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Tank BY-105 is on the Ferrocyanide Watch List. Samples were collected from Tank BY-105 using the vapor sampling system (VSS) on July 7, 1994 by WHC Sampling and Mobile Laboratories. The tank headspace temperature was determined to be 26 C. Air from the Tank BY-105 headspace was withdrawn via a heated sampling probe mounted in riser 10A, and transferred via heated tubing to the VSS sampling manifold. All heated zones of the VSS were maintained at approximately 65 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, Pacific Northwest Laboratories, and Oregon Graduate Institute of Science and Technology through a contract with Sandia National Laboratories. The 46 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 10 trip blanks provided by the laboratories.

Tank BY-110 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Tank BY-110 is on the Ferrocyanide Watch List. Samples were collected from Tank BY-110 using the vapor sampling system (VSS) on November 11, 1994 by WHC Sampling and Mobile Laboratories. The tank headspace temperature was determined to be 27 C. Air from the Tank BY-110 headspace was withdrawn via a 7.9 m-long heated sampling probe mounted in riser 12B, and transferred via heated tubing to the VSS sampling manifold. All heated zones of the VSS were maintained at approximately 50 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, and Pacific Northwest Laboratories. The 40 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 14 trip blanks and 2 field blanks that accompanied the samples.

The Clean Air Act Amendments of 1990 identify a number of hazardous air pollutants (HAPs) as candidates for regulation. Should regulations be imposed on HAP emissions from coal-fired power plants, a sound understanding of the fundamental principles controlling the formation and partitioning of toxic species during coal combustion will be needed. With support from the Federal Energy Technology Center (FETC), the Electric Power Research Institute, and VTT (Finland), Physical Sciences Inc. (PSI) has teamed with researchers from USGS, MIT, the University of Arizona (UA), the University of Kentucky (UK), the University of Connecticut (UC), the University of Utah (UU) and the University of North Dakota Energy and Environ-mental Research Center (EERC) to develop a broadly applicable emissions model useful to regulators and utility planners. The new Toxics Partitioning Engineering Model (ToPEM) will be applicable to all combustion conditions including new fuels and coal blends, low-NOx combustion systems, and new power generation plants. Development of ToPEM will be based on PSI's existing Engineering Model for Ash Formation (EMAF). This report covers the reporting period from 1 January 1999 to 31 March 1999. During this period, a full Program Review Meeting was held at the University of Arizona. At this meeting, the …