This document summarizes the status of sample fabrication and analysis in the Form Development Sample Test Matrix. Since its publication in the ''Baseline Formulation'' report (UCRL-ID- 133089, PIP-99-O 12) and in the ''Complete Single-Phase Sample Fabrications that Support the Licensing Application and Complete Process and Compositional Extreme Sample Fabrications that Support the Licensing Application'' report (PIP-99-078), the Sample Test Matrix has been updated and expanded. This version is current though September 30, 1999.

We have begun building the ''Mercury'' laser system as the first in a series of new generation diode-pumped solid-state lasers for inertial fusion research. Mercury will integrate three key technologies: diodes, crystals, and gas cooling, within a unique laser architecture that is scalable to kilojoule and megajoule energy levels for fusion energy applications. The primary near-term performance goals include 10% electrical efficiencies at 10 Hz and 100J with a 2-10 ns pulse length at 1.047 mm wavelength. When completed, Mercury will allow rep-rated target experiments with multiple chambers for high energy density physics research.

This document describes characterization needs for the DOE waste feed processing and disposal management of TWRS Privatization Phase I. The DOE must obtain information to evaluate and minimize risk associated with the private contractor's design phase deliverables (April 2000); authorization to proceed with Part B-2 (August 2000); and start of treatment facility construction (July 2001). Additionally, the DOE must ensure that the contract feed and product specifications are adequate and achievable, and that there is a sufficient basis for negotiating the price for. services. The purpose of this Data Quality Objective (DQO) is to provide data to accomplish the following: (1) update waste characterization information from source tanks to provide an independent assessment that the specifications and Interface Control Documents (ICDS) are adequate for DOE's management of the site M&I contractor and private contractor contracts; (2) provide preliminary information for the private contractor's process and facility designs and DOE's review of the designs in preparation for the authorization to proceed with Phase I Part B-2; (3) provide preliminary information for ILAW and IHLW storage and disposal design/specifications; (4) support update of the ILAW performance assessment (PA) for disposal; (5) help substantiate the ability to (1) comply with U.S. Nuclear Regulatory …

Characterization of Offgas Generated During Calcination of Incinerator Ash Surrogates

This report examines two radiation detection technologies (superheated droplet detectors and bubble chambers) in detail and answers the question of how they can be or should be adapted for use in national security applications.

This Phase II final report documents the Phase II testing conducted from June 18, 1998 through November 13, 1998, and it focuses on the application of the siphon technology as a sub-component of the overall GeoSiphon Cell technology. [Q-TPL-T-00004]

'The HSV in storage in MTF has been monitored during FY99, and its overpressure has been sampled and analyzed. The HSV''s internal pressure continues to rise slowly, and the overpressure still analyzes as 100 percent 3He. The titanium tritide sample that was to be monitored annually and which had developed a leak last year has been repaired and isotherms measured. Unfortunately the sample was showing significant unexpected 3He release, so the isotherm data is corrupted by unknown levels of 3He. This release has disqualified this sample for future use, as it is now seriously divergent from the HSV material. A different sample must be selected for subsequent studies.The unexpected 3He releases of the Ti-3 sample and the possible release in other Ti samples have raised a serious issue. It should be determined why this release is occurring, so that an unexpected release of 3He during HSV unloading can be assessed as unlikely.'

This report lists the steps that are required to calculate deceleration ramps for all relevant Accumulator devices. The ramps used for the 1996-97 fixed target run (experiment E835) are saved in files associated with ACNET console application PA1627 (PAUX RAMP DEVELOP). These ramps cannot be re-used because the Accumulator {gamma}{sub t} upgrade has significantly changed the lattice since the last time the ramps were used. Consequently, new deceleration ramps must be calculated and commissioned before the next fixed target run. The deceleration ramp for a particular device is a table that gives the sequence of set values sent to the device as the ramp is executed. The 1997 ramps consist of ramp tables for 100 devices. Appendix 1 gives a list of the devices ramped. Most of these devices will still require ramps for the next fixed target run. Future decelerations will also require ramps for the quadrupole magnet shunts that were installed as part of the {gamma}{sub t} upgrade. Additionally, ramps must be constructed for the two skew-sextupole magnets that will be installed during the summer of 1999.

'The HSV in storage in MTF has been monitored during FY99, and its overpressure has been sampled and analyzed. The HSV''s internal pressure continues to rise slowly, and the overpressure still analyzes as 100 percent 3He. The titanium tritide sample that was to be monitored annually and which had developed a leak last year has been repaired and isotherms measured. Unfortunately the sample was showing significant unexpected 3He release, so the isotherm data is corrupted by unknown levels of 3He. This release has disqualified this sample for future use, as it is now seriously divergent from the HSV material. A different sample must be selected for subsequent studies.The unexpected 3He releases of the Ti-3 sample and the possible release in other Ti samples have raised a serious issue. It should be determined why this release is occurring, so that an unexpected release of 3He during HSV unloading can be assessed as unlikely.'

This report is a recommendation from the Kalispel Tribe to the Bonneville Power Administration (BPA) and the Columbia Basin Fish and Wildlife Authority (CBFWA) for management of the Pend Oreille Wetland Wildlife Mitigation project II (Dilling Addition) for the extensive habitat losses caused by Albeni Falls Dam on Kalispel Ceded Lands. Albeni Falls Dam is located on the Pend Oreille River near the Washington-Idaho border, about 25 miles upstream of the Kalispel Indian Reservation. The dam controls the water level on Lake Pend Oreille. The lake was formerly the center of subsistence use by the Kalispel Tribe. Flooding of wetlands, and water fluctuations both on the lake and downstream on the river, has had adverse impacts to wildlife and wildlife habitat. An extensive process was followed to formulate and prioritize wildlife resource goals. The Kalispel Natural Resource Department provided guidance in terms of opportunities onsite. To prioritize specific goals, the Albeni Falls Interagency Work Group and the Columbia Basin Fish and Wildlife Authority Wildlife Caucus were consulted. From this process, the top priority goal for the Kalispel Tribe is: Protect and develop riparian forest and shrub, and freshwater wetlands, to mitigate losses resulting from reservoir inundation and river level fluctuations …

This report is descriptive journey of the 2nd Generation PFBC Systems R&D Phase 2 AND Phase 3.

The Monitored Geologic Repository Waste Package Operations of the Civilian Radioactive Waste Management System Management & Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Navy (Refs. 1 and 2). The Navy SNF has been considered for disposal at the potential Yucca Mountain site. For some waste packages, the containment may breach (Ref. 3), allowing the influx of water. Water in the waste package may moderate neutrons, increasing the likelihood of a criticality event within the waste package. The water may gradually leach the fissile components and neutron absorbers out of the waste package. In addition, the accumulation of silica (SiO{sub 2}) in the waste package over time may further affect the neutronics of the system. This study presents calculations of the long-term geochemical behavior of waste packages containing the Enhanced Design Alternative (EDA) II inner shell, Navy canister, and basket components. The calculations do not include the Navy SNF in the waste package. The specific study objectives were to determine the chemical composition of the water and the quantity of silicon (Si) and other solid corrosion products in the waste package during the first million years after the waste package …

The purpose of this calculation is to evaluate the structural response of the standard high-level waste (HLW) canister and the HLW canister containing the cans of immobilized plutonium (''can-in-canister'' throughout this document) to the drop event during the handling operation. The objective of the calculation is to provide the structure parameter information to support the canister design and the waste handling facility design. Finite element solution is performed using the commercially available ANSYS Version (V) 5.4 finite element code. Two-dimensional (2-D) axisymmetric and three-dimensional (3-D) finite element representations for the standard HLW canister and the can-in-canister are developed and analyzed using the dynamic solver.

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The vector potential, magnetic field and stored energy of a quadrupole magnet array are derived. Each magnet within the array is a current sheet with a current density proportional to the azimuthal angle 2{theta} and the longitudinal periodicity (2m-1){pi}/L. Individual quadrupoles within the array are oriented in a way that maximizes the field gradient The array does not have to be of equal spacing and can be of a finite size, however when the array is equally spaced and is of infinite size the solution can be simplified. We note that whereas, in a single quadrupole magnet with a current density proportional to cos2{theta} the gradient is pure, such purity is not preserved in a quadrupole array.

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An overview of the U.S. Department of Energy Office of Codes and Standards programs to establish minimum efficiency codes, standards, and guidelines for reduced energy use and lower operating costs in U.S. building components.

Backfills have been part of Sandia National Laboratories' [Sandia's] Waste Isolation Pilot Plant [WIPP] designs for over twenty years. Historically, backfill research at Sandia has depended heavily on the changing mission of the WIPP facility. Early testing considered heat producing, high level, wastes. Bentonite/sand/salt mixtures were evaluated and studies focused on developing materials that would retard brine ingress, sorb radionuclides, and withstand elevated temperatures. The present-day backfill consists of pure MgO [magnesium oxide] in a pelletized form and is directed at treating the relatively low contamination level, non-heat producing, wastes actually being disposed of in the WIPP. It's introduction was motivated by the need to scavenging CO{sub 2} [carbon dioxide] from decaying organic components in the waste. However, other benefits, such as a substantial desiccating capacity, are also being evaluated. The MgO backfill also fulfills a statutory requirement for assurance measures beyond those needed to demonstrate compliance with the US Environmental Protection Agency [EPA] regulatory release limits. However, even without a backfill, the WIPP repository design still operates within EPA regulatory release limits.

The objective of this analysis is to develop a proposed repository subsurface layout for ''Design Alternative No.2: Low Thermal Load, 25 MTU/Acre at 38 Meter Drift Spacing''. The scope of this analysis covers: (1) Integration of the Exploratory Studies Facility (ESF) openings into the proposed repository layout for Design Alternative No.2. (2) Identification and incorporation of factors influencing the proposed repository layout. These factors include the required drift spacing, total required emplacement length, the number of emplacement drifts, required development, and subsurface ventilation. (3) Geometry and configuration of the proposed repository openings. Development of a proposed layout showing the required emplacement area.

An overview of the voluntary network of community partnerships joined with the US Department of Energy to improve the energy efficiency of their communities buildings.

During the course of experiments involving high explosives, (HE), alignment lasers are often employed where the laser beam impinges upon a metal encased HE sample or on the bare HE itself during manned operations. While most alignment lasers are of low enough power so as not to be of concern, safety questions arise when considering the maximum credible power output of the laser in a failure mode, or when multiple laser spots are focused onto the experiment simultaneously. Safety questions also arise when the focused laser spot size becomes very small, on the order of 100 {micro}m or less. This paper addresses these concerns by describing a methodology for determining safety margins for laser impingement on metal encased HE as well as one for bare HE. A variety of explosives encased in Al, Cu, Ta and stainless steel were tested using the first of these techniques. Additional experiments were performed using the second method where the laser beam was focused directly on eight different samples of pressed-powder HE.

An overview of the U.S. Department of Energy Office of State and Community Programs activities and partnership approaches.

This contribution proposes strawman techniques for Security Service Discovery by ATM endsystems in ATM networks. Candidate techniques include ILMI extensions, ANS extensions and new ATM anycast addresses. Another option is a new protocol based on an IETF service discovery protocol, such as Service Location Protocol (SLP). Finally, this contribution provides strawman requirements for Security-Based Routing in ATM networks.

An overview of past research achievements, current research, and future research focus of the U.S. Department of Energy's Office of Building Technology, State and Community Programs.