Prior to 1988, a variety of materials were buried on the US DOE Oak Ridge Reservation. Records of the disposal operations are incomplete and toxic materials may have been placed adjacent to potential explosives. One of the safety concerns in conducting an environmental restoration project at the burial sites, is the possibility of an explosion which could release toxic materials to the atmosphere. A safety analysis examined the consequences of such releases by first postulating an upper bound for the strength of an explosive. A correlation, developed by Steindler and Seefeldt of Argonne National Laboratory, was then used to estimate the amount and particle-size distribution of the material that could become airborne from the explosion. The estimated amount of airborne material was the source term in an atmospheric dispersion model which was used to calculate infinite-time, concentration-time integrals and 5-minute, time- weighted average concentrations at locations down-wind from the explosion. The dispersion model includes particle deposition as a function of particle-size distribution class. The concentration-time integrals and average concentrations were compared to published guidelines to assess the consequences of an accidental explosion.

A FORTRAN subroutine for the calculation of the ac electrical conductivity in two-temperature, strongly coupled, overdense plasma is presented. The routine is the result of a model calculation based on classical transport theory with application to plasmas created by the interaction of short pulse lasers and solids. The formulation is analytic and the routine is self-contained.

The objectives of this project are to continue reservoir characterization of the Cypress Sandstone; to identify and map facies-defined waterflood units (FDWS); and to design and implement water-alternating-gas (WAG) oil recovery utilizing carbon dioxide (CO{sub 2}) The producibility problems are permeability variation and poor sweep efficiency. Part 1 of the project focuses on the development of computer-generated geological and reservoir simulation models that will be used to select sites for the demonstration and implementation of CO{sub 2} displacement programs in Part 2. Included in Part 1 is the site selection and drilling of an infill well, coring of the Cypress interval, and injectivity testing to gather information used to update the reservoir simulation model. Part 2 involves field implementation of WAG. Technology Transfer includes outreach activity such as seminars, workshops, and field trips.

The overall objective of the project is to develop and optimize a two-stage fermentation process for the conversion of coal derived synthesis gas in an mixture of alcohols. The goals include the development of superior strains with high product tolerance and productivity, optimization of process conditions for high volumetric productivity and product concentrations, integration and optimization of two stage syngas fermentation, evaluation of bioreactor configurations for enhanced mass transfer, evaluation of syngas conversion by a culture of Butyribacterium methyltrophicum and Clostridium acetobutylicum, development of a membrane based pervaporation system for in situ removal of alcohols, and development of a process for reduction of carbon and electron loss. The specific goals for year one (September 1992 - September 1993) were (1) development of a project work plan, (2) development of superior CO-utilizing strains, (3) optimization of process conditions for conversion of synthesis gas to a mixture of acids in a continuously stirred reactor (CSTR), (4) evaluation of different bioreactor configurations for maximization of mass transfer of synthesis gas, (5) development of a membrane based pervaporation system, and (6) reduction of carbon and electron loss via H{sub 2}CO{sub 2} fermentation. Experimentation and progress toward these goals are described in this report.

Operation of a pilot-scale system for continuous metallothermic reduction of uranium tetrafluoride (UF{sub 4} or green salt) has been initiated. This activity is in support of the development of a cost- effective process to produce uranium-iron (U-Fe) alloy feed for the Uranium-Atomic Vapor Laser Isotope Separation (U-AVLIS) program. To date, five runs have been made to reduce green salt (UF{sub 4}) with magnesium. During this quarter, three runs were made to perfect the feeding system, examine feed rates, and determine the need for a crust breaker/stirrer. No material was drawn off in any of the runs; both product metal and by-product salt were allowed to accumulate in the reactor.

With recent theoretical and empirical research in basic and applied psychology, human factors, and engineering, it is now sufficient to define an integrated approach to the deign of advanced displays for present and future nuclear power plants. Traditionally, the conventional displays have shown operators the individual variables on gauges, meters, strip charts, etc. This design approach requires the operators to mentally integrate the separately displayed variables and determine the implications for the plant state. This traditional approach has been known as the single-sensor-single-indicator display design and it places an intolerable amount of mental workload on operators during transients and abnormal conditions. This report discusses a new alternative approach which is the use of direct perception interfaces. Direct perception a interfaces display the underlying physical and system constraints of the situation in a directly perceptual way, such that the viewer need not reason about what is seen to identify system states, but can identify the state of the system perceptually. It is expected that displays which show the dynamics of fundamental physical laws should better support operator decisions and diagnoses of plant states. The purpose of this research project is to develop a suite of direct perception displays for PWR nuclear …

This purpose of this document is to provide: a record of site visits, a summary of the comments received from the user survey forms and site interviews, a description of the manual process used for personnel security clearances. The participants in the user survey and site surveys were users at: DOE contractor clearance offices (LLNL), DOE operations offices (ORO,Y-12, Albuquerque ,Sandia, San Francisco) Office of Personnel Management (OPM) - Federal Investigations Processing Center (FIPC).

Making self-assessment a ``cultural norm`` at the DOE Office of Energy Research (ER) laboratories has been a tremendous challenge. In an effort to provide a forum for the ER laboratories to share their self-assessment program implementation experiences, the Lawrence Berkeley Laboratory hosted a Self-Assessment Workshop: July 1993. The workshop was organized to cover such areas as: DOE`s vision of self-assessment; what makes a workable program; line management experiences; how to identify root causes and trends; integrating quality assurance, conduct of operations, and self-assessment; and going beyond environment, safety, and health. Individuals from the ER laboratories wishing to participate in the workshop were invited to speak on topics of their choice. The workshop was organized to cover general topics in morning presentations to all attendees and to cover selected topics at afternoon breakout sessions. This report summarizes the presentations and breakout discussions.

Coupon immersion tests were performed on ASTM A537 Class 1 carbon steel in simulated DWPF recycle solutions at 90 [+-] 2[degrees]C, as part of the continuing effort to investigate the formation of shock-sensitive deposits. Coupons were partially immersed for four months in solutions of the same composition used previously at SRTC and at the DuPont Engineering Test Center (a salt solution containing 0.5 M hydroxide and 0.043 M nitrite). Shock-sensitive deposits were not seen on the coupons from this test. There was considerable general corrosion above the water line due to condensate and distilled water contact of the steel. New immersion tests are being planned for completion by September, 1993. The new test solution will reflect the recycle stream chemistry changes brought about by planned ammonia scrubbing in the DWPF.

Coupon immersion tests were performed on ASTM A537 Class 1 carbon steel in simulated DWPF recycle solutions at 90 {+-} 2{degrees}C, as part of the continuing effort to investigate the formation of shock-sensitive deposits. Coupons were partially immersed for four months in solutions of the same composition used previously at SRTC and at the DuPont Engineering Test Center (a salt solution containing 0.5 M hydroxide and 0.043 M nitrite). Shock-sensitive deposits were not seen on the coupons from this test. There was considerable general corrosion above the water line due to condensate and distilled water contact of the steel. New immersion tests are being planned for completion by September, 1993. The new test solution will reflect the recycle stream chemistry changes brought about by planned ammonia scrubbing in the DWPF.

The United States produced just over 1 billion short tons of coal in 1992, 0.4 percent more than in 1991. Most of the 4-million-short-ton increase in coal production occurred west of the Mississippi River, where a record level of 408 million short tons of coal was produced. The amount of coal received by domestic consumers in 1992 totaled 887 million short tons. This was 7 million short tons more than in 1991, primarily due to increased coal demand from electric utilities. The average price of delivered coal to each sector declined by about 2 percent. Coal consumption in 1992 was 893 million short tons, only 1 percent higher than in 1991, due primarily to a 1-percent increase in consumption at electric utility plants. Consumer coal stocks at the end of 1992 were 163 million short tons, a decrease of 3 percent from the level at the end of 1991, and the lowest year-end level since 1989. US coal exports fell 6 percent from the 1991 level to 103 million short tons in 1992. Less coal was exported to markets in Europe, Asia, and South America, but coal exports to Canada increased 4 million short tons.

Structural analyses of large precision cathode strip chambers performed up to the date of this publication are documented. Mechanical property data for typical chamber materials are included. This information, originally intended to be an appendix to the {open_quotes}CSC Structural Design Bible,{close_quotes} is presented as a guide for future designers of large chambers.

To identify, document, and maintain the Uranium Mill Tailings Remedial Action (UMTRA) Project`s environment, safety, and health (ES&H) regulatory requirements, the US Department of Energy (DOE) UMTRA Project Office tasked the Technical Assistance Contractor (TAC) to develop a regulatory operating envelope for the UMTRA Project. The system selected for managing the UMTRA regulatory operating envelope data bass is based on the Integrated Project Control/Regulatory Compliance System (IPC/RCS) developed by WASTREN, Inc. (WASTREN, 1993). The IPC/RCS is a tool used for identifying regulatory and institutional requirements and indexing them to hardware, personnel, and program systems on a project. The IPC/RCS will be customized for the UMTRA Project surface remedial action and groundwater restoration programs. The purpose of this plan is to establish the process for implementing and maintaining the UMTRA Project`s regulatory operating envelope, which involves identifying all applicable regulatory and institutional requirements and determining compliance status. The plan describes how the Project will identify ES&H regulatory requirements, analyze applicability to the UMTRA Project, and evaluate UMTRA Project compliance status.

The fatigue and fracture properties of U6Nb were measured to provide the materials property data needed for structural designs in material processed by solution quenching and aging 200 C/2h. Limited testing was also performed on as-quenched U6Nb. The authors have extended the database on fatigue properties in U6Nb to include both crack initiation data and crack propagation data. The static load carrying capabilities have been characterized through fracture toughness and tensile property measurements. Using a rotating beam fatigue machine, a fatigue strength of 248 MPa was measured at 10{sup 8} cycles for smooth bars at zero mean load. As is typical of nonferrous alloys, U6Nb does not exhibit a fatigue endurance limit. Reductions in fatigue strength for notched bars and for mean loads of 276 MPa and 483 MPa (70 ksi) were also determined. The predominant sites for fatigue crack initiation were identified as niobium carbide and uranium oxide inclusion clusters and the distribution of these inclusions are presented. Fatigue crack propagation rates were measured in the near-threshold regime using compact tension specimens. The fatigue threshold for crack growth rates below 10{sup {minus}7} mm/cycle were measured at both R = 0.1, for which a fatigue threshold of 3.2 MPa{radical}m was …

Diffusion-bonded NiAl-Al[sub 2]O[sub 3] and Ni[sub 3]Al-Al[sub 2]O[sub 3] couples were thermally fatigued at 900 C for 1500 and 3500 cycles. The fiber-matrix interface weakened after 3500 cycles for the Saphikon fibers, while the Altex, PRD-166, and FP fibers showed little, if any, degradation. Diffusion bonding of fibers to Nb matrix is being studied. Coating the fibers slightly increases the tensile strength and has a rule-of-mixtures effect on elastic modulus. Push-out tests on Sumitomo and FP fibers in Ni aluminide matrices were repeated. Al[sub 2]O[sub 3] was evaporated directly from pure oxide rod onto acoustically levitated Si carbide particles, using a down-firing, rod-fed electron beam hearth; superior coatings were subsequently produced using concurrent irradiation with 200-eV argon ion-assist beam. The assist beam produced adherent films with reduced tensile stresses. In diffusion bonding in B-doped Ni[sub 3]Al matrices subjected to compressive bonding at 40 MPa at 1100 C for 1 hr, the diffusion barriers failed to prevent catastrophic particle- matrix reaction, probably because of inadequate film quality. AlN coatings are currently being experimented with, produced by both reactive evaporation and by N[sup +]-ion enhanced deposition. A 3-kW rod-fed electron-beam-heated evaporation source has been brought into operation.

Diffusion-bonded NiAl-Al{sub 2}O{sub 3} and Ni{sub 3}Al-Al{sub 2}O{sub 3} couples were thermally fatigued at 900 C for 1500 and 3500 cycles. The fiber-matrix interface weakened after 3500 cycles for the Saphikon fibers, while the Altex, PRD-166, and FP fibers showed little, if any, degradation. Diffusion bonding of fibers to Nb matrix is being studied. Coating the fibers slightly increases the tensile strength and has a rule-of-mixtures effect on elastic modulus. Push-out tests on Sumitomo and FP fibers in Ni aluminide matrices were repeated. Al{sub 2}O{sub 3} was evaporated directly from pure oxide rod onto acoustically levitated Si carbide particles, using a down-firing, rod-fed electron beam hearth; superior coatings were subsequently produced using concurrent irradiation with 200-eV argon ion-assist beam. The assist beam produced adherent films with reduced tensile stresses. In diffusion bonding in B-doped Ni{sub 3}Al matrices subjected to compressive bonding at 40 MPa at 1100 C for 1 hr, the diffusion barriers failed to prevent catastrophic particle- matrix reaction, probably because of inadequate film quality. AlN coatings are currently being experimented with, produced by both reactive evaporation and by N{sup +}-ion enhanced deposition. A 3-kW rod-fed electron-beam-heated evaporation source has been brought into operation.

We have completed a fifteen year, referenced and documented compilation of more than 15,000 measurements of laser-induced damage thresholds (LIDT) conducted at the Lawrence Livermore National Laboratory (LLNL). These measurements cover the spectrum from 248 to 1064 nm with pulse durations ranging from < 1 ns to 65 ns and at pulse-repetition frequencies (PRF) from single shots to 6.3 kHz. We emphasize the changes in LIDTs during the past two years since we last summarized our database. We relate these results to earlier data concentrating on improvements in processing methods, materials, and conditioning techniques. In particular, we highlight the current status of anti-reflective (AR) coatings, high reflectors (HR), polarizers, and frequency-conversion crystals used primarily at 355 nm and 1064 nm.

This was the fifth quarter of the contract. During this quarter we (1) got approval for the NEPA requirements related to the field work, (2) placed the subcontract for the field data acquisition, (3) completed the field work, and (4) began processing the seismic data. As already reported, the field data acquisition was at Acomo`s Powder River Basin site in southeast Wyoming. This is a low permeability fractured site, with both gas and oil present. The reservoir is highly compartmentalized, due to the low permeability, with the fractures providing the only practical drainage paths for production. The two formations of interest are: The Niobrara: a fractured shale and limey shale to chalk, which is a reservoir rock, but also its own source rock. The Frontier: a tight sandstone lying directly below the Niobrara, brought into contact with it by an unconformity. The fractures are thought to lie in a roughly northwest-southeast trend, along the strike of a flexure, which forms one of the boundaries of the basin.

As part of the integrated verification experiment (IVE), we deployed a network of hf ionospheric sounders to detect the effects of acoustic waves generated by surface ground motion following underground nuclear tests at the Nevada Test Site. The network sampled up to four geographic locations in the ionosphere from almost directly overhead of the surface ground zero out to a horizontal range of 60 km. We present sample results for four of the IVEs: Misty Echo, Texarkana, Mineral Quarry, and Bexar.

As part of the integrated verification experiment (IVE), we deployed a network of hf ionospheric sounders to detect the effects of acoustic waves generated by surface ground motion following underground nuclear tests at the Nevada Test Site. The network sampled up to four geographic locations in the ionosphere from almost directly overhead of the surface ground zero out to a horizontal range of 60 km. We present sample results for four of the IVEs: Misty Echo, Texarkana, Mineral Quarry, and Bexar.

An ion exchange unit has been manufactured for WSRC by British Nuclear Fuels, Ltd. This unit consists of three columns, ancillary valving, pumps, lines, and computer controls. It has been delivered to TNX for use in testing a cesium-specific ion exchange resin, developed at WSRC as a potential second generation process for the decontamination of Defense Waste Processing Facility (DWPF) supernate. This resin also has Department of Energy applications at both Oak Ridge and Hanford. Oak Ridge is interested in decontaminating the Melton Valley storage tank supernate, while Hanford is interested in decontaminating the 101-AW and 101-SY supernate streams. Another potential developmental interest is the Savannah River Site (SRS) DWPF recycle stream. The three primary waste streams of interest are the Oak Ridge, Hanford, and SRS, SWPF supernate streams. For these three waste streams, the cesium decontamination factor (DF) will be measured for a non-radioactive, simulated, high-level waste solution. The test objectives, process outlines, and broad characterization of the waste streams are described.

A new test method was developed which showed the installed In- Tank Precipitation Filter Unit {number_sign}3 provided at least 40, 000 x decontamination of the precipitated potassium tetraphenylborate (KTPB) during the cold chemical runs.This filter is expected to meet the needed 40,000 x hot cesium decontamination requirements, assuming that the cesium precipitate, CsTPB, behaves the same as KTPB. The new method permits cold chemicals field testing of installed filters to quantify particulate decontamination and verify filter integrity before going hot. The method involves a 1000 x concentration of fine particulate KTPB in the filtrate to allow direct analysis by counting for naturally radioactive isotope K-40 using the underground SRTC gamma spectroscopy facility. The particulate concentration was accomplished by ultra filtration at Rhone-Poulenc, NJ, using a small cross-flow bench facility, followed by collection of all suspended solids on a small filter disc for K analysis.

Existing ITP filtrate hold tanks may provide sufficient capacity and residence time to strip dissolved benzene from the incoming filtrate using nitrogen sparging in the bottom of the old tanks. This is based on equilibrium supported by late Wash test data using aged washed slurry. Theoretical considerations indicate that benzene stripping will be more difficult from the ITP unwashed high salt filtrates due to reduced mass transfer. Therefore experimental sparging data is needed to quantify the theoretical effects.Foaming limits which dictate allowable sparging rate will also have to be established. Sparging in the hold tanks will require installation of sintered metal spargers, and possibly stirrers and foam monitoring/disengagement equipment. The most critical sparging needs are at the start of the precipitation/concentration cycle, when the filtrate flux rate is the highest,and at the end of wash cycle where Henry`s equilibrium constant falls off,requiring more gas to sparge the dissolved benzene. With adequate recycle (for proper distribution) or sparging in the old tanks, the 30 inch column could be used for the complete ITP process. A courser packing would reduce back pressure while enabling benzene stripping. The Late Wash Tests indicate adequate benzene stripping even at reduced gas flow. This will require …

In order to reach the high fluence goals of the Beamlet laser at Lawrence Livermore National Laboratory (LLNL), the polarizers in the system must be laser conditioned to increase their damage thresholds. Research has shown that by using a six-step raster-conditioning program, the damage thresholds of the HfO{sub 2}/SiO{sub 2} multilayer polarizer coatings can be increased to meet the Beamlet 3-ns design goal of 8 J/cm{sub 2}. Because of the large size of the polarizers (73 cm {times} 37 cm {times} 9 cm), a large-area conditioning facility was constructed capable of rastering a one-meter optic, weighing as much as 400 pounds, at any specified use angle. A large translational stage moves the optic in a raster pattern through a stationary, 10-Hz rep-rated, 1064-nm beam with 10-ns pulses. A scatter measurement diagnostic allows on-the-fly evaluation of laser-induced damage and logs the coordinates of the damage. Laser energy is measured pulse-to-pulse in order to ensure stability during a scan. A small amount of minor coating damage does occur during the process, but the damage does not grow upon further irradiation. This damage causes only a small increase in total scatter compared to that due to the preexisting defects, and would not influence …