The overall electrolyte concentration in the NFE environment is expected to be somewhere between 1X and saturated J-13 well water. This covers more than three orders-of-magnitude in chloride anion concentration. The pH of this solution is expected to be somewhere between 5 and 10. Exposed patches of the CRM could see this environment.

The overall electrolyte concentration in the NFE environment is expected to be somewhere between 1X and saturated J-13 well water. This covers more than three orders-of-magnitude in chloride anion concentration. The pH of this solution is expected to be somewhere between 5 and 10. Exposed patches of the CRM could see this environment.

This report presents the results of the independent certified public accountants` audit of the Western Area Power Administration`s combined power system statements of assets, Federal investment and liabilities, and the related combined statements of revenues, expenses and accumulated net revenues, and cash flows. The auditors` report on Westerns internal control structure disclosed three new reportable conditions concerning the lack of: (1) a reconciliation of stores inventory from subsidiary ledgers to summary financial information, (2) communication of interest during construction and related adjustments to interest on Federal investment, and (3) a system to prevent and detect power billing errors. None of the conditions were considered to be material weaknesses. Western provided concurrence and corrective action plans. The auditors` report on Western`s compliance with laws and regulations also disclosed two new instances of noncompliance. Western failed to calculate nonreimbursable expenses in accordance with the Grand Canyon Protection Act and had an unexplained difference in gross Federal investment balances used to calculate interest on Federal investment. Western provided concurrence and corrective action plans for the instances.

Experimental Breeder Reactor-II (EBR-II), an experimental sodium cooled fast breeder reactor located at Argonne National Laboratory-West (ANL-W), was shut down in 1994, and has since been defueled in preparation for final plant closure. Approximately 100,000 gallons of liquid sodium is contained in the primary and secondary cooling systems of the EBR-II plant. The liquid sodium must be drained from the reactor systems during closure of the plant to place the reactor plant in an industrially and radiologically safe condition for long term storage or dismantlement. Because the liquid sodium is a listed waste under the Resource Conservation Recovery Act (RCRA), it is not suitable for disposal. It therefore must be transferred to the Sodium Process Facility (SPF), which is located approximately nine hundred feet from the reactor complex, where it will be processed into a non-reactive form, suitable for land disposal in Idaho. To facilitate this transfer, a heated pipeline for carrying liquid sodium metal from EBR-II to the SPF was designed and installed. The SPF was originally designed and built to process primary sodium from the Fermi-1 reactor. The sodium is stored at ANL-W in 55 gallon drums. Design of the SPF did not originally accommodate processing of EBR-II …

High-temperature fracture strength and compressive creep of an electrodischarge-machinable composite, Al{sub 2}O{sub 3}-30.9 vol.% SiC whiskers-23 vol.% TiC particles have been studied to 1200 C and 1450 C, respectively, in inert atmosphere. Microstructures of fractured and deformed specimens were examined by scanning and transmission electron microscopy. Fast fracture occurred at T {le} 1200 C. Steady-state creep was achieved for T > 1350 C at stresses < 80 MPa, with the rate-controlling mechanism being partially unaccommodated grain-boundary sliding, with a stress exponent of {approx}1 and an activation energy of {approx}470 kJ/mol.

The purpose of the studies conducted at Argonne National Laboratory is to understand the impact mental representational systems have in identifying how user comfort parameters influence how information is to best be presented. By understanding how each individual perceives information based on the three representational systems (visual, auditory and kinesthetic modalities), it has been found that a different approach must be taken in the design of interfaces resulting in an outcome that is much more effective and representative of the users mental model. This paper will present current findings and future theories to be explored.

Process designs and economics were developed to produce LNG and liquid carbon dioxide (CO{sub 2}) from landfill gas (LFG) using the Acrion CO{sub 2} wash process. The patented Acrion CO{sub 2} wash process uses liquid CO{sub 2} to absorb contaminants from the LFG. The process steps are compression, drying, CO{sub 2} wash contaminant removal and CO{sub 2} recovery, residual CO{sub 2} removal and methane liquefaction. Three flowsheets were developed using different residual CO{sub 2} removal schemes. These included physical solvent absorption (methanol), membranes and molecular sieves. The capital and operating costs of the flowsheets were very similar. The LNG production cost was around ten cents per gallon. In parallel with process flowsheet development, the business aspects of an eventual commercial project have been explored. The process was found to have significant potential commercial application. The business plan effort investigated the economics of LNG transportation, fueling, vehicle conversion, and markets. The commercial value of liquid CO{sub 2} was also investigated. This Phase 1 work, March 1998 through February 1999, was funded under Brookhaven National laboratory contract 725089 under the research program entitled ``Liquefied Natural Gas as a Heavy Vehicle Fuel.'' The Phase 2 effort will develop flowsheets for the following: (1) …

This report summarizes the results of a full-scale demonstration of a high density polyethylene (HDPE) package, manufactured by Arrow Construction, Inc. of Montgomery, Alabama. The HDPE package, called ARROW-PAK, was designed and patented by Arrow as both a method to macroencapsulation of radioactively contaminated lead and as an improved form of waste package for treatment and interim and final storage and/or disposal of drums of mixed waste. Mixed waste is waste that is radioactive, and meets the criteria established by the United States Environmental Protection Agency (US EPA) for a hazardous material. Results from previous testing conducted for the Department of Energy (DOE) at the Idaho National Engineering Laboratory in 1994 found that the ARROW-PAK fabrication process produces an HDPE package that passes all helium leak tests and drop tests, and is fabricated with materials impervious to the types of environmental factors encountered during the lifetime of the ARROW-PAK, estimated to be from 100 to 300 years. Arrow Construction, Inc. has successfully completed full-scale demonstration of its ARROW-PAK mixed waste macroencapsulation treatment unit at the DOE Hanford Site. This testing was conducted in accordance with Radiological Work Permit No. T-860, applicable project plans and procedures, and in close consultation with …

Proteins are remarkable molecular machines that are essential for life. They can do many things ranging from the precise control of blood clotting to synthesizing complex organic compounds. Pictures of protein molecules are in high demand in biotechnology because they are important for applications such as drug discovery and for engineering enzymes for commercial use. X-ray crystallography is the most common method for determining the three-dimensional structures of protein molecules. When a crystal of a protein is placed in an X-ray beam, scattering of X-rays off the ordered molecules produces a diffraction pattern that can be measured on a position-sensitive CCD or image-plate detector. Protein crystals typically contain thousands of atoms and the diffraction data are generally measured to relatively low resolution. Consequently the direct methods approaches generally cannot be applied. Instead, if the crystal is modified by adding metal atoms at specific sites or by tuning the wavelength of the X-rays to cross an absorption edge of a metal atom in the crystal, then the information from these additional measurements is sufficient to first identify the /locations of the metal atoms. This information is then used along with the diffraction data to make a three-dimensional picture of electron densities. …

Electron-beam physical vapor deposition (EBPVD) of tooling metal, onto a shaped substrate to produce a replica of the substrate surface, offers the potential for significant cost savings over present methods of injection mold manufacturing. These savings are realized by the high deposition rate and the corresponding short manufacturing times provided by the EBPVD process. However, on route to realizing these gains, there are process technical issues which need to be resolved. Mold surfaces typically contain relatively high aspect ratio details that must be replicated to dimensional tolerances within +/- 2 mils. The deposited mold material must also provide high surface hardness and high fracture toughness. Good quality grain structure can be obtained in deposited Al 10-wt% Cu mold material when the substrate and corresponding deposit are at high process temperature. However, the resulting mold is subject to distortion during cooldown due to differential temperatures and shrinkage rates. Thermally controlled cooldown and the use of crushable substrate materials reduce these distortions, but not to the required levels of tolerance. Deposition of the Al-Cu at lower temperature produces columnar, poorly joined grains which result in a brittle and weakened mold material. When Al 10-wt% Cu metal vapor is deposited across high aspect …

A Vertical Seismic Profile (VSP) was recorded in Rye Patch by LBNL between December 11 and December 13, 1997. Figure 1 shows the location of the Rye Patch Geothermal Field with Well 46-28 located within the marked Rye Patch Anomaly. The VSP in Well 46-28 used a vibroseis source and a single-level, high temperature, hydraulic wall-locking, 3-component seismometer. The vibroseis source was a Mertz P-wave vibrator. The source sweep was 10 Hz to 80 Hz, 10 seconds long, with a 0.2 s cosine taper. The borehole geophone was an SSC model LVHK 6001 using 14 Hz geophones. The recording system was a Geometrics Strataview. Six data channels were recorded: the three geophones, the source pilot, the vibrator reference and the vibrator baseplate accelerometer. The record length was 12,288 samples at a 1 ms sample rate, giving a 2.3 s correlated record length. A 10 Hz low cut filter was used and no high cut filter was used except the anti-alias filter. Results are described.

Lawrence Livermore National Laboratory (LLNL) examined the waste stream from a water jet cutting operation, to evaluate the possible reuse of waste garnet sand. The sand is a cutting agent used to shape a variety of materials, including metals. Nearly 70,000 pounds of waste sand is generated annually by the cutting operation. The Environmental Protection Department evaluated two potential reuses for the spent garnet sand: backfill in utility trenches; and as a concrete constituent. In both applications, garnet waste would replace the sand formerly purchases by LLNL for these purposes. Findings supported the reuse of waste garnet sand in concrete, but disqualified its proposed application as trench backfill. Waste sand stabilized in ac concrete matrix appeared to present no metals-leaching hazard; however, unconsolidated sand in trenches could potentially leach metals in concentrations high enough to threaten ground water quality. A technical report submitted to the San Francisco Bay Regional Water Quality Control Board was reviewed and accepted by that body. Reuse of waste garnet cutting sand as a constituent in concrete poured to form walkways and patios at LLNL was approved.

This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-T-110. This report supports the requirements of the Tri-Party Agreement Milestone M-44-15B. Tank 241-T-110 is listed on the Hydrogen Watch List.

The objectives were to determine the elastic constants of thin films deposited on substrates, to measure residual stress and to detect and characterize defects in thin film substrate configurations. There are many present and potential applications of configurations consisting of a thin film deposited on a substrate. Thin films that are deposited to improve the hardness and/or the thermal properties of surfaces were of principal interest in this work. Thin film technology does, however, also include high {Tc} superconductor films, films for magnetic recording, superlattices and films for band-gap engineering and quantum devices. The studies that were carried out on this project also have relevance to these applications. Both the film and the substrate are generally anisotropic. A line-focus acoustic microscope has been used to measure the speed of surface acoustic waves (SAW) in the thin film/substrate system. This microscope has unique advantages for measurements in anisotropic media. Analytical and numerical techniques have been employed to extract the desired information on the thin film from the measured SAW data. Results include: (1) analytical and numerical techniques for the direct problem and for inverse methods; (2) measurements of homogeneous and superlattice film constants; (3) investigation of the effect of surface roughness …

Comparison study to determine the feasibility of performing two different options for calculations of radionuclide transport.

This analysis estimates the radiation dose to the equipment that will be submerged in double-shell tank waste. The results of this analysis are intended to be the basis for specifications for in-tank equipment. The scope of this analysis is limited to the new equipment required for the delivery of waste feed to Phase 1 private contractors. Phase 1 refers to the first of a two-phase plan to privatize the remediation of Hanford`s tank waste. The focus of this analysis is on waste feed delivery because of the extraordinarily high cost of any failure that would lead to the interruption of a steady flow of feed to the private contractors.

This report presents the results of the independent certified public accountants` audit of the Federal Energy Regulatory commission`s statements of financial position, and the related statements of operations and changes in net position. The auditors` work was conducted in accordance with generally accepted government auditing standards. An independent public accounting firm conducted the audit. The auditors` reports on the Commission`s internal control structure and compliance with laws and regulations disclosed no reportable conditions or instances of noncompliance.

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Seventeen remote-handled (RH) transuranic (TRU) waste canisters currently are stored in vertical, underground shafts at Technical Area (TA)-54, Area G, at Los Alamos National Laboratory (LANL). These 17 RH TRU waste canisters are destined to be shipped to the Waste Isolation Pilot Plant (WIPP) for permanent disposal in the geologic repository. As the RH TRU canister is likely to be the final payload container prior to placement into the 72-B cask and shipment to the WIPP, these waste canisters provide a unique opportunity to ascertain representative flammable gas concentrations in packaged RH-TRU waste. Hydrogen, which is produced by the radiolytic decomposition of hydrogenous constituents in the waste matrix, is the primary flammable gas of concern with RH TRU waste. The primary objectives of the experiment that is described by this test plan are to sample and analyze the waste canister headspace gases to determine the concentration of hydrogen in the headspace gas and to calculate the hydrogen gas generation rate for comparison to the applicable maximum allowable hydrogen generation rate (mole/sec) limits. It is a goal of this experiment to determine the headspace gas concentrations of other gases (e.g., oxygen, nitrogen, carbon dioxide, carbon monoxide, and volatile organic compounds (VOCs) …

This Cold Run test is designed to demonstrate the functionality of systems necessary to move waste drums throughout the plant using approved procedures, and the compatibility of these systems to function as an integrated process. This test excludes all internal functions of the gloveboxes. In the interest of efficiency and support of the facility schedule, the initial revision of the test (rev 0) was limited to the following: Receipt and storage of eight overpacked drums, four LLW and four TRU; Receipt, routing, and staging of eleven empty drums to the process area where they will be used later in this test; Receipt, processing, and shipping of two verification drums (Route 9); Receipt, processing, and shipping of two verification drums (Route 1). The above listed operations were tested using the rev 0 test document, through Section 5.4.25. The document was later revised to include movement of all staged drums to and from the LLW and TRU process and RWM gloveboxes. This testing was performed using Sections 5.5 though 5.11 of the rev 1 test document. The primary focus of this test is to prove the functionality of automatic operations for all mechanical and control processes listed. When necessary, the test demonstrates …

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A nuclear weapons identification system (NWIS), under development since 1984 at the Oak Ridge Y-12 Plant and presently in use there, uses active neutron interrogation with low-intensity {sup 252}Cf sources in ionization chambers to provide a timed source of fission neutrons from the spontaneous fission of {sup 252}Cf. To date, measurements have been performed on {approximately}15 different weapons systems in a variety of configurations both in and out of containers. Those systems included pits and fully assembled systems ready for deployment at the Pantex Plant in Amarillo, Texas, and weapons components at the Oak Ridge Y-12 Plant. These measurements have shown that NWIS can identify nuclear weapons and/or components; nuclear weapons/components can be distinguished from mockups where fissile material has been replaced by nonfissile material; omissions of small amounts (4%) of fissile material can be detected; changes in internal configurations can be determined; trainer parts can be identified as was demonstrated by verification of 512 containers with B33 components at the Y-12 Plant (as many as 32 in one 8-hour shift); and nonfissile components can be identified. The current NWIS activities at the Oak Ridge Y-12 Plant include: (1) further development of the system for more portability and lower power …

Amrita is a software system for automating numerical investigations. The system is driven using its own powerful scripting language, Amrita, which facilitates both the composition and archiving of complete numerical investigations, as distinct from isolated computations. Once archived, an Amrita investigation can later be reproduced by any interested party, and not just the original investigator, for no cost other than the raw CPU time needed to parse the archived script. In fact, this entire lecture can be reconstructed in such a fashion. To do this, the script: constructs a number of shock-capturing schemes; runs a series of test problems, generates the plots shown; outputs the LATEX to typeset the notes; performs a myriad of behind-the-scenes tasks to glue everything together. Thus Amrita has all the characteristics of an operating system and should not be mistaken for a common-or-garden code.

This report describes the methodology used in conducting the Cold Vacuum Drying Facility (CVDF) hazard analysis to support the CVDF phase 2 safety analysis report (SAR), and documents the results. The hazard analysis was performed in accordance with DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, and implements the requirements of US Department of Energy (DOE) Order 5480.23, Nuclear Safety Analysis Reports.