During the IDMS noble-metal demonstration runs ammonium nitrate deposition was found in the vessel vent system of the feed preparation area. In the bench-scale experiments of studying the hydrogen generation during the sludge treatment cycle, ammonium ion production was also monitored. It was found that: During a simulation of the DWPF Cold Chemical Runs SRAT cycle no detectable amount of ammonium ions was generated when treating a non-noble-metal containing sludge simulant according to the nitric acid flowsheet. Ammonium ions were generated during the SRAT-SME cycle when treating the noble-metal containing sludge with either formic acid or nitric acid/late-washing PHA. This is due to the reaction between formic acid and nitrate catalyzed by the noble metals in the sludge simulant. Ammonium ion production closely followed the hydrogen evolution from the catalytic decomposition of formic acid. This report summarizes the results of the production of ammonia during the SRAT cycle.

This document outlines a detection-level groundwater monitoring program for the state-approved land disposal structure (SALDS). The SALDS is an infiltration basin proposed for disposal of treated effluent from the 200 Areas of the Hanford Site. The purpose of this plan is to present a groundwater monitoring program that is capable of determining the impact of effluent disposal at the SALDS on the quality of groundwater in the uppermost aquifer. This groundwater monitoring plan presents an overview of the SALDS, the geology and hydrology of the area, the background and indicator evaluation (detection) groundwater monitoring program, and an outline of a groundwater quality assessment (compliance) program. This plan does not provide a plan for institutional controls to track tritium beyond the SALDS.

A waste minimization program to develop a non-oxidative stripper system based on metallic getters is being conducted. Initial development is being performed using a Zr-Fe-Sn intermetallic alloy getter procured as Stl98 from SAES Gefters/USA., Inc. This memorandum describes characterizations of physical and compositional properties of SAES Stl98. SAES Stl98 getter was supplied as very durable, cylindrical pellets made by compaction of. granules of Zr-Fe-Sn alloy up to 150 [mu]m in size. Pellet density was 5.2 g/mL corresponding to 24.8% open porosity and very little closed porosity. Bulk composition of Stl98 was 73.6 weight percent (w/o) Zr, 23.3 w/o Fe and 1.2 w/o Sn. Stl98 consists of Zr[sub 2]Fe primary phase along with four secondary phases (ZrFe[sub 2], Zr[sub 5]FeSn, [alpha]-zirconium, and [eta]-Zr[sub 4]Fe[sub 2]O[sub 0.6]). Hydriding characteristics of Stl98 are expected to differ slightly from those of Zr[sub 2]Fe because [alpha]-zirconium and, possibly, Zr[sub 5]FeSn also react with hydrogen.

During the IDMS noble-metal demonstration runs ammonium nitrate deposition was found in the vessel vent system of the feed preparation area. In the bench-scale experiments of studying the hydrogen generation during the sludge treatment cycle, ammonium ion production was also monitored. It was found that: During a simulation of the DWPF Cold Chemical Runs SRAT cycle no detectable amount of ammonium ions was generated when treating a non-noble-metal containing sludge simulant according to the nitric acid flowsheet. Ammonium ions were generated during the SRAT-SME cycle when treating the noble-metal containing sludge with either formic acid or nitric acid/late-washing PHA. This is due to the reaction between formic acid and nitrate catalyzed by the noble metals in the sludge simulant. Ammonium ion production closely followed the hydrogen evolution from the catalytic decomposition of formic acid. This report summarizes the results of the production of ammonia during the SRAT cycle.

Calculated curves of cable-in-conduit conductor energy stability margins vs. current are compared to experimental curves obtained at Oak Ridge National Laboratory for NbTi single triplex conductors. The conductors ranged in length from 1.8 m to 4.8 m, and had no imposed helium flow. The initiating heat pulse was applied for 16.7 ms over the entire conductor length. The calculated stability curves display the large decrease in energy margin from the low current and high energy margin {open_quotes}well-cooled{close_quotes} stability region, to the high current and low energy margin {open_quotes}ill-cooled{close_quotes} region that was determined experimentally. The calculated {open_quotes}limiting current{close_quotes} of 250 A (boundary between the ill-cooled and well-cooled regions) also agrees with experiment. The multi-valued stability margins measured for lengths of 3.1 and 3.8 m could not be obtained by the computer model. Excluding the multiple stabilities, the calculated margins are generally 30% lower than the experimental values. The decrease in energy margin in the ill-cooled region was found to be due to the low critical to operating temperature difference (2.2 K at 250 A). This prevents an initiating pulse in the ill-cooled region from being able to generate significant Joule heating without quenching, limiting the energy margin.

The purpose of this document is to present the details of the calculations used to define the radionuclide inventory for the Department of Energy (DOE) spent nuclear fuel (SNF) used in the TSPA-VA calculations.

None

A human simulation environment, the Virtual Human (VH), is under development at the Oak Ridge National Laboratory (ORNL). Virtual Human connects three-dimensional (3D) anatomical models of the body with dynamic physiological models to investigate a wide range of human biological and physical responses to stimuli. We have utilized the Java programming language to develop a flexible user interface to the VH. The Java prototype interface has been designed to display dynamic results from selected physiological models, with user control of the initial model parameters and ability to steer the simulation as it is proceeding. Taking advantage of Java�s Remote Method Invocation (RMI) features, the interface runs as a Java client that connects to a Java RMI server process running on a remote server machine. The RMI server can couple to physiological models written in Java, or in other programming languages, including C and FORTRAN. Future versions of the interface will be linked to 3D anatomical models of the human body to complete the development of the VH.

The Hazard Analysis Database was developed in conjunction with the hazard analysis activities conducted in accordance with DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, for the Tank Waste Remediation System (TWRS) Final Safety Analysis Report (FSAR). The FSAR is part of the approved TWRS Authorization Basis (AB). This document describes, identifies, and defines the contents and structure of the TWRS FSAR Hazard Analysis Database and documents the configuration control changes made to the database. The TWRS Hazard Analysis Database contains the collection of information generated during the initial hazard evaluations and the subsequent hazard and accident analysis activities. The database supports the preparation of Chapters 3,4, and 5 of the TWRS FSAR and the USQ process and consists of two major, interrelated data sets: (1) Hazard Evaluation Database--Data from the results of the hazard evaluations; and (2) Hazard Topography Database--Data from the system familiarization and hazard identification.

N Reactor fuel elements stored in the Hanford K Basins were subjected to high temperatures and vacuum conditions to remove water. Results of the first series of whole element furnace tests i.e., Runs 1 through 8 were collected in this summary report. The report focuses on the six tests with breached fuel from the K West Basin which ranged from a simple fracture at the approximate mid-point to severe damage with cladding breaches at the top and bottom ends with axial breaches and fuel loss. Results of the tests are summarized and compared for moisture released during cold vacuum drying, moisture remaining after drying, effects of drying on the fuel element condition, and hydrogen and fission product release.

This test report documents the successful inspection and testing to certify two NuPac PAS-1 casks in accordance with US Department of Energy Certificate of Compliance (CoC) USA/9184/B(U). The primary and secondary containment vessels of each cask met the acceptance criteria defined in the CoC and the test plan.

None

Recent instrumentation developments in photoemission are providing new insights into the physics of complex materials. With increased energy and momentum resolution, it has become possible to examine in detail different contributions to the self-energy or inverse lifetime of the photohole created in the photoexcitation process, Employing momentum distribution and energy distribution curves, a detailed study of the optimally doped cuprate, Bi{sub 2}Sr{sub 2}CaCu{sub 2}O{sub g+{delta}}, shows that the material behaves like a non-Fermi liquid with no evidence for the quasi-particles characteristic of a Fermi liquid.

The Benchmark Project was created from a desire to identify best practices and improve the overall efficiency and performance of the Y-12 Plant's systems and personnel supporting the manufacturing mission. The mission of the benchmark team was to search out industry leaders in manufacturing and evaluate their engineering practices and processes to determine direction and focus for Y-12 modernization efforts. The companies visited included several large established companies and a new, small, high-tech machining firm. As a result of this effort, changes are recommended that will enable Y-12 to become a more modern, responsive, cost-effective manufacturing facility capable of supporting the needs of the Nuclear Weapons Complex (NWC) into the 21st century. The benchmark team identified key areas of interest, both focused and general. The focus areas included Human Resources, Information Management, Manufacturing Software Tools, and Standards/Policies and Practices. Areas of general interest included Infrastructure, Computer Platforms and Networking, and Organizational Structure. The results of this benchmark showed that all companies are moving in the direction of model-based engineering and manufacturing. There was evidence that many companies are trying to grasp how to manage current and legacy data. In terms of engineering design software tools, the companies contacted were somewhere …

Switched-capacitor analog memories are well-suited to a number of applications where a continuous digitization of analog signals is not needed. In data acquisition systems based on the use of an analog memory, the input waveforms are sampled and stored at a high rate for a limited period of time, and the analog samples are then retrieved at a lower rate and digitized with a slow ADC before new waveforms are acquired. The advantages of using an analog memory are lower overall power dissipation and cost, higher density and reliability, and potentially superior performance. The analog memory essentially exploits the fact that the sampling and storage of samples in a bank of analog memory cells can be accomplished at a higher rate and with a greater precision than direct digital conversion. This dissertation examines the important components of an analog memory in detail and investigates their use in a number of architectures. The research has led to the design of an analog memory that can acquire analog waveforms at sampling rates of several hundred MHz with a dynamic range and linearity of more than 12 bits, without the need for elaborate calibration and correction procedures. This is accomplished by means of …

'The overall goal of the research program is to develop a better understanding of the physical and chemical factors and processes influencing fate and transport of immiscible and dissolved-phase dense solvents in groundwater in fractured, highly weathered clays and shales. These widespread materials are much different, physically and chemically, from granular soils or fractured low porosity rocks, which are the media used for most previous investigations of solvent behavior. The investigations are needed to provide a basic scientific framework for assessment of solvent transport and remediation in fractured clay-rich deposits. Specific experimental objectives include: (1) Determine the nature and distribution of porosity in these materials, and its influence on pressure-saturation behavior for immiscible solvents. This includes determining values for entry pressure, residual saturation, fracture aperture and matrix pore size distribution, as well as assessment of methodologies for measuring/characterizing these parameters. (2) Determine the influence of dissolution, sorption and diffusion into the matrix on long term disappearance of residual solvents in the fractured materials. (3) Assessment of the potential for natural attenuation of common solvents, especially TCE, in these deposits. This includes investigating the natural geochemistry and microbiology of the deposits, and assessing biologically-mediated degradation of solvents in the laboratory and …

We are interested in the stability of three-dimensional fluid flows to small dkturbances. One computational approach is to solve a sequence of large sparse generalized eigenvalue problems for the leading modes that arise from discretizating the differential equations modeling the flow. The modes of interest are the eigenvalues of largest real part and their associated eigenvectors. We discuss our work to develop an effi- cient and reliable eigensolver for use by the massively parallel simulation code MPSalsa. MPSalsa allows simulation of complex 3D fluid flow, heat transfer, and mass transfer with detailed bulk fluid and surface chemical reaction kinetics.

This paper discusses a search for nuclei containing two strange quarks performed at Brookhaven National Laboratory. The goals and approach of experiment E885 are reviewed. Preliminary missing mass spectra for a subset of the data are presented, showing sensitivity for {Xi} hypernuclei and H particle searches. Existence of an angular correlation between pions in the sequential decay of {Lambda}{Lambda} hypernuclei is suggested on theoretical grounds.

The basic structure of the LANL Environmental Restoration (ER) Site Ranking System and its use are described in this document. A related document, Instructions for Generating Inputs for the LANL ER Site Ranking System, contains detailed descriptions of the methods by which necessary inputs for the system will be generated. LANL has long recognized the need to provide a consistent basis for comparing the risks and other adverse consequences associated with the various waste problems at the Lab. The LANL ER Site Ranking System is being developed to help address this need. The specific purpose of the system is to help improve, defend, and explain prioritization decisions at the Potential Release Site (PRS) and Operable Unit (OU) level. The precise relationship of the Site Ranking System to the planning and overall budget processes is yet to be determined, as the system is still evolving. Generally speaking, the Site Ranking System will be used as a decision aid. That is, the system will be used to aid in the planning and budgetary decision-making process. It will never be used alone to make decisions. Like all models, the system can provide only a partial and approximate accounting of the factors important to …

Pursuant to Section 1340(c) of the Energy Policy Act of 1992 (EPACT), this report presents the Secretary of Energy`s review of data collected by the Federal Government on rates for rail and pipeline transportation of domestic coal, oil, and gas for the years 1988 through 1997, and proposals to develop an adequate data base for each of the fuels, based on the data availability review. This report also presents the Energy Information Administration`s findings regarding the extent to which any Federal agency is studying the impacts of the Clean Air Act Amendments of 1990 (CAAA90) and other Federal policies on the transportation rates and distribution patterns of domestic coal, oil, and gas.

A waste minimization program to develop a non-oxidative stripper system based on metallic getters is being conducted. Initial development is being performed using a Zr-Fe-Sn intermetallic alloy getter procured as Stl98 from SAES Gefters/USA., Inc. This memorandum describes characterizations of physical and compositional properties of SAES Stl98. SAES Stl98 getter was supplied as very durable, cylindrical pellets made by compaction of. granules of Zr-Fe-Sn alloy up to 150 {mu}m in size. Pellet density was 5.2 g/mL corresponding to 24.8% open porosity and very little closed porosity. Bulk composition of Stl98 was 73.6 weight percent (w/o) Zr, 23.3 w/o Fe and 1.2 w/o Sn. Stl98 consists of Zr{sub 2}Fe primary phase along with four secondary phases (ZrFe{sub 2}, Zr{sub 5}FeSn, {alpha}-zirconium, and {eta}-Zr{sub 4}Fe{sub 2}O{sub 0.6}). Hydriding characteristics of Stl98 are expected to differ slightly from those of Zr{sub 2}Fe because {alpha}-zirconium and, possibly, Zr{sub 5}FeSn also react with hydrogen.

Synthetic washed ITP slurry (200 g) was oven dried for three days at 60--65{degrees}C in a pan, to a hard solid that stuck to the pan bottom. Between the cracks that formed were a few small particles of unknown size. The solids that were stuck to the pan bottom were pried free and repetitively ground in a mortar and pestle until they all passed through a 40 mesh sieve. This product was then sieved into 50, 80, 100, 170, 200, 325 sieve fractions and the results plotted. A protion of the fines passing the 325 sieve were further separated by air flotation in a glass tube with fritted bottom. Increasing amounts of air were passed up through the tube that floated out increasing fractions of particles after weighing. ITP washed precipitate, ground and dried, had a particle size distribution versus cumulative weight fraction curve between Powered coal and Filter sand. The minimum particle size was about 20 microns.

The HM Process (modified PUREX) has been used in the H-Canyon since 1959 to recover uranium and byproduct neptunium. The PUREX process has been used in the Separation facilities in F and H-Area. This report analyzes both the inhalation and ingestion radionuclide dose impact of the HM and PUREX process soluble portion of their waste streams. The spent fuel assemblies analyzed are the Mark 16B, Mar 22 for the HM process, and the Mark 31A, Mark 31B for the PUREX process. The results from this analysis are combined with an analysis of the current Safety Analysis Report SAR source term to evaluate source terms for HLW supernate. Analysis of fission yield data and SAR source term values demonstrates that a limited number of radionuclides contribute 1% or more to the total dose and that cesium and plutonium isotopes are the radionuclides with major impact in the supernate source term. This report analyses both volatile and evaporative impact as recommended by DOE guidance. In reality, the only radionuclide volatilized during evaporative conditions is tritium. No evidence of selective volatility occurs during forced evaporation in HLW. The results obtained permit reducing the list of radionuclides to be considered in the development of …

The Pennsylvania State University is conducting a superclean coal-water slurry (SCCWS) program for the United States Department of Energy (DOE) and the Commonwealth of Pennsylvania with the objective of determining the capability of effectively firing SCCWS in an industrial boiler designed for oil. Penn State has entered into a cooperative agreement with DOE to determine if SCCWS (a fuel containing coal with 3.0 wt.% ash and 0.9 wt.% sulfur) can effectively be burned in an oil-designed industrial boiler without adverse impact on boiler rating, maintainability, reliability, and availability. The project will provide information on the design of new systems specifically configured to fire these clean coal-based fuels. The project consists of four phases: (1) design, permitting, and test planning, (2) construction and start up, (3) demonstration and evaluation (1,000-hour demonstration), and (4) program expansion (additional 1,000 hours of testing). The boiler testing will determine if the SCCWS combustion characteristics, heat release rate, fouling and slagging behavior, corrosion and erosion limits, and fuel transport, storage, and handling characteristics can be accommodated in an oil-designed boiler system. In addition, the proof-of-concept demonstration will generate data to determine how the properties of SCCWS and its parent coal affect boiler performance. Economic factors associated …