A system to measure the tunes of a single antiproton (or proton) bunch was built and has been commissioned. The system achieved high sensitivity with a novel closed-orbit suppression system. The use of high bandwidth directional pickpus and kickers in conjunction with precise timing gates enabled the measurement of the tune of a single bunch.

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A side view of the double sided ladder is shown in Figure 1. There are two types of double sided ladder; 6 chip and 9 chip. The 6 chip ladder has three SVX II chips mounted directly opposite the cooling channel and 3 chips mounted at the ladder end. The 9 chip ladder has 4 SVX II chips directly opposite the cooling channel and 5 chips at the ladder end. The power density is highest in the 6 chip ladder. All plots and calculations in this Engineering Note pertain to the 6 chip ladder with the understanding that the 9 chip temperature profile is somewhat improved over the 6 chip due to the reduced power density in the row of chips opposite the cooling channel. The two dimensional finite difference technique used for these calculations is described in DOEN 447 and will not be described here. The assumed thermal conductivity of beryllium is 190 W/m-K, and that of silicon is 149 W/m-K. The SVX II power dissipation is assumed 0.400 W. There is no cable or hybrid component power dissipation in this set of simulations. The epoxy in the glue joints consists of 2 mils thickness of thermally conductive epoxy …

This report the addresses German Military Presence in the United States. The United States has a long history of training with its allies, both here and abroad. Germany first began training its pilots in the United States in 1955.1 The scope of these training programs has grown ever since. Many analysts argue that the most important benefit of an increasing German military presence in the United States may be to enhance opportunities for cooperation at a time when the United States has dramatically reduced its military presence in Europe.

This report provides an overview of the economic/political developments in Vietnam, including their relationship with the United States.

The Department of Energy (DOE) has expressed a need for an on-line, real-time instrument for assaying alpha-emitting radionuclides (uranium and the transuranics) in effluent waters leaving DOE sites to ensure compliance with regulatory limits. Due to the short range of alpha particles in water ({approximately}40 Tm), it is necessary now to intermittently collect samples of water and send them to a central laboratory for analysis. A lengthy and costly procedure is used to separate and measure the radionuclides from each sample. Large variations in radionuclide concentrations in the water may go undetected due to the sporadic sampling. Even when detected, the reading may not be representative of the actual stream concentration. To address these issues, Tecogen, a division of Thermo Power Corporation, a Thermo Electron company, is developing a real-time, field-deployable, alpha monitor based on a solid-state silicon wafer semiconductor (patent pending, to be assigned to the Department of Energy). The Thermo Alpha Monitor (TAM) will serve to monitor effluent water streams (Subsurface Contaminants Focus Area) and will be suitable for process control of remediation as well as decontamination and decommissioning operations, such as monitoring scrubber or rinse water radioactivity levels (Mixed Waste Focus Area and D&D Focus Area). It …

A training and qualification program for nuclear criticality safety technical staff personnel has been developed and implemented. The program is compliant with requirements and provides evidence that a systematic approach has been taken to indoctrinate new technical staff. Development involved task analysis to determine activities where training was necessary and the standard which must be attained to qualify. Structured mentoring is used where experienced personnel interact with candidates using checksheets to guide candidates through various steps and to provide evidence that steps have been accomplished. Credit can be taken for the previous experience of personnel by means of evaluation boards which can credit or modify checksheet steps. Considering just the wealth of business practice and site specific information a new person at a facility needs to assimilate, the program has been effective in indoctrinating new technical staff personnel and integrating them into a productive role. The program includes continuing training.

The TWRS System Engineering (SE) process and information flows are described using a process modeling methodology. The results of this activity, and the next phase of developing a normalized data model, will be used in training and implemented in SE information systems and support tools.

The purpose of this Documentation and Analysis for Packaging (DAP) is to certify that the packaging system currently in use for the 100 B and C Area large scale excavation and remediation campaign, meets the intent of U.S. Department of Transportation(DOT) requirements for bulk packaging (49 CFR 173.427) of radioactive materials, up to and including low specific activity (LSA) I quantities of Class 7 material.

Ground-penetrating radar was used at three locations in an attempt to locate and determine the depth of the 216-U-1/2 pipeline. Many anomalies were found, all very useful to the project, but only some of which were identified with the pipeline.

This document summarizes the information on the historical uses, present status and the sampling and analysis results of waste stored in Tank 241-BX-110. This reports supports the requirements of Tri-Party Agreement Milestone M-44-09.

This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-B-204. This report supports the requirements of Tri-Party Agreement Milestone M-44-09.

The Equipment Qualification Test described in this test procedure document is the acceptance test procedure (ATP) for the LDUA Baseline System. It verifies that the equipment is complete and in working order, and demonstrates its readiness for being deployed into an actual underground storage tank.

The concentrations of mercury at the FAVC inlet and exit were measured during the BL1 and PX6 runs of the Integrated DWPF Melter System (IDMS) with the HEME bypassed and without the ammonia scrubber. The results showed that mercury concentrations of approximately 1.02-12.7 (mean 5.74) times saturation occurred at the FAVC exit. The concentration of mercury at the FAVC inlet was found to be 0.66-6.2 times the saturation value (based on the SRAT condenser exit). In the PX7 run, the ammonia scrubber was used and the FAVC HEME was not bypassed. The results from this run showed that the FAVC inlet concentrations again were above saturation (1.45-15.5 times saturation), but that the FAVC exit concentrations were only 0.02-0.41 times saturation (except for one data point at 1.61 times saturation). Operation of the FAVC without the HEME could therefore result in FAVC exit mercury concentrations of greater than 5.74 times saturation, which would result in DWPF emitting greater than 405 lb/yr of mercury at 100 percent attainment; this quantity is well in excess of the permit limit of 175 lb/yr (for all of DWPF). However, with the HEME in place, the emissions are predicted to be only about 40 lb/yr for …

This Subsystem Design Requirement (SSDR) document establishes the performance, design, and verification requirements `for the conventional building systems and subsystems of the Optics Assembly Building (OAB). These building system requirements are associated with housing and supporting the operational flow of personnel and materials throughout the OAB for preparing and repairing optical and mechanical components used in the National Ignition Facility (NIF) Laser and Target Building (LTAB). This SSDR addresses the following subsystems associated with the OAB: * Structural systems for the building spaces and operational-support equipment and building- support equipment. * Architectural building features associated with housing the space, operational cleanliness, and functional operation of the facility. * Heating, Ventilating, and Air Conditioning (HVAC) systems for maintaining a clean and thermally stable ambient environment within the facility. * Plumbing systems that provide potable water and sanitary facilities for the occupants and stormwater drainage for transporting rainwater. * Fire Protection systems that guard against fire damage to the facility and its contents. * Material handling equipment for transferring optical assemblies and other materials within building areas and to the LTAB. * Mechanical process piping systems for liquids and gases that provide cooling, cleaning, and other service to optical and mechanical components. …

The K East Basin contains open-top canisters with up to fourteen N Reactor fuel assemblies distributed between the two barrels of each canister. Each fuel assembly generally consists of inner and outer concentric elements fabricated from uranium metal with zirconium alloy cladding. The canisters also contain varying amounts of accumulated sludge. Retrieval of sample fuel elements and associated sludge for examination is scheduled to occur in the near future. The purpose of this document is to specify particular canisters and elements of interest as candidate sources of fuel and sludge to be shipped to laboratories.

We present details of a model for calculating the mass spectrum of light-quark mesons and decay constants of the pseudoscalar meson octet from a phenomenological model based on Dyson-Schwinger and Bethe-Salpeter equations. In this model the Bethe-Salpeter kernel is approximated by a separable ansatz obtained from input quark propagators. 13 refs., 2 tabs.

Solid waste forecast volumes to be generated or received ;at Westinghouse Hanford Company`s Solid Waste program over the life cycle of the site are described in this report. Previous forecast summary reports have covered only a 30-year period; however, the life-cycle approach was adopted for this FY 1996 report to ensure consistency with waste volumes reported in the 1996 Multi-Year Program Plans (MYPP). The volume data were collected on a life-cycle basis from onsite and offsite waste generators who currently ship or plan to ship solid waste to the Solid Waste program. The volumes described in detail are low-level mixed waste (LLMW) and transuranic/transuranic-mixed (TRU(M)) waste. The volumes reported in this document represent the external volume of the containers selected to ship the waste. Summary level information pertaining to low-level waste (LLW) is described in Appendix B. Hazardous waste volumes are also provided in Appendices E and F but are not described in detail since they will be managed by a commercial facility. Emphasis is placed on LLMW and TRU(M) waste because it will require processing and storage at Hanford Solid Waste`s Central Waste Complex (CORK) prior to final disposal. The LLW will generally be sent directly to disposal. The …

We explore the capability of a 500 or 1000 GeV e{sup +} e{sup {minus}} linear collider to measure anomalous quartic gauge boson couplings. In the framework of a non-linear effective Lagrangian with a custodial SU(2) symmetry, there are only two next-to-leading order operators which contribute to quartic, but not to two- and three-gauge boson interactions. The limits on the coefficients of these operators from present and future e{sup +} e{sup {minus}} colliders are compared with those available from other sources.

Tests were conducted at Hoosier Energy`s Merom Station 535-MW Units 1 and 2 wet limestone flue gas desulfurization (FGD) systems to evaluate options for achieving high SO{sub 2} removal efficiency. The options tested included use of dibasic acid (DBA) and sodium formate additives as well as operation at higher reagent ratios (higher pH set points). In addition to the tested options, the effectiveness of other potential options was simulated using the Electric Power Research Institute`s FGD Process Integration and Simulation Model (FGDPRISM) after it was calibrated to the system. An economic analysis was done to determine the cost effectiveness of each option. A summary of results is given on the following: SO{sub 2} removal performance; additive consumption; and SO{sub 2} removal upgrade economics.

Methods for limiting the size of hadronic spin-flip in the Coulomb- Nuclear Interference. region are critically assessed. This work was presented at the High Energy Polarimetry Workshop in Amsterdam, Sept. 9, 1996 and the RHIC Spin Collaboration meeting in Marseille, Sept. 17, 1996.

In order to develop a system for a large scale coal solubilization and its bioconversion to utilizable fuel, the author plans to clone the genes encoding Neurospora protein that facilitate depolymerization of coal. He also plans to use desulfurizing bacteria to remove the sulfur in situ and use other microorganisms to convert biosolubilized coal into utilizable energy following an approach utilizing several microorganisms. In addition the product of coal solubilized by fungus will be characterized to determine their chemical nature and the mechanism of reaction catalyzed by fungal product during in vivo and in vitro solubilization by the fungus or purified fungal protein.

The authors present direct measurements of the Z{sup 0}-lepton coupling asymmetries, A{sub e}, A{sub {mu}}, and A{sub {tau}}. It is based on a data sample selected from 170 k Z{sup 0} decays collected by the SLD detector. The Z`s are produced by collisions of polarized e{sup {minus}} with unpolarized e{sup +} bunches at SLC. The couplings are extracted from the measurement of the left-right forward-backward asymmetry for each lepton species. The preliminary results (using information from all leptonic data for A{sub e}) are: A{sub e} = 0.148 {+-} 0.016, A{sub {mu}} = 0.102 {+-} 0.033 and A{sub {tau}} = 0.190 {+-} 0.034.

This safety evaluation for packaging (SEP) provides the analysis and authorization to transport high-activity waste from the 324 Facility to PUREX, using the SEG 3-82B Type B cask. For the proposed campaign, the payload has larger quantities of radioactive material, is not fissile-exempt, and has higher decay heat loads than that specified by the 3-82B cask certificate of compliance. No changes will be made to the current design of the packaging. Onsite transport of the package with the higher source term will be authorized by this SEP to demonstrate equivalent safety of the package, as specified in PNL-MA-81, Hazardous Material Shipping Manual.