The purpose of this Acceptance Test Report is to provide documentation for the acceptance testing of the rotary mode core sample trucks 3 and 4, designated as HO-68K-4600 and HO-68K-4647, respectively. This report conforms to the guidelines established in WHC-IP-1026, ``Engineering Practice Guidelines,`` Appendix M, ``Acceptance Test Procedures and Reports.`` Rotary mode core sample trucks 3 and 4 were based upon the design of the second core sample truck (HO-68K-4345) which was constructed to implement rotary mode sampling of the waste tanks at Hanford. Successful completion of acceptance testing on June 30, 1995 verified that all design requirements were met. This report is divided into four sections, beginning with general information. Acceptance testing was performed on trucks 3 and 4 during the months of March through June, 1995. All testing was performed at the ``Rock Slinger`` test site in the 200 West area. The sequence of testing was determined by equipment availability, and the initial revision of the Acceptance Test Procedure (ATP) was used for both trucks. Testing was directed by ICF-KH, with the support of WHC Characterization Equipment Engineering and Characterization Project Operations. Testing was completed per the ATP without discrepancies or deviations, except as noted.

During the assembly of major components into the D0 Detector, a transfer bridge was required to move the North-End Calorimeter from the clean room,over the cable bridge and onto the north sidewalk of the assembly hall. This experiment is now at the beginning stages of the next phase, namely the upgrade of this Detector for future physics research. A major piece of this upgrade is the installation of a solenoid magnet into the Central Calorimeter. In order to accomplish this, the South End Calorimeter has to be removed from the detector and the North End Calorimeter must be moved an additional 20-inch from its nominal open position (total 60-inch movement). The South End Calorimeter will be removed from the detector using the equipment designed for its installation. The calorimeter will be staged on the south sidewalk during the installation of the solenoid magnet and the central tracking systems. The North End Calorimeter is moved 60-inch to give more space between calorimeters during magnet, tracker and cable installation work. This movement will allow the calorimeter to remain coupled to the cryo system. However, this movement requires an extension be added to the center beam. This extension will support the rear wheels …

We consider unusual events in the CDF and D0 dilepton+jets sample with very high ET(lepton) and ET(missing). It is possible, but very unlikely, that these events originate from top quark pair production; however, they have characteristics that are better accounted for by decays of supersymmetric quarks with mass in the region of 300 GeV.

This Acceptance Test Report presents the results of the acceptance test performed at the vendor shop on the monitors and control functions of the A-101 Saltwell Pumping PICS skid. This work supports the interim stabilization of tank 241-A-101.

This Acceptance Test Report presents the results of the acceptance test performed at the shop on the monitor and control functions of the AX-101 Saltwell Pumping PICS skid. This work supports the interim stabilization of tank 241-AX-101.

This report addresses the ATR power supplies.

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) as specified in the Waste Package Implementation Plan (pp. 4-8, 4-11, 4-24, 5-1, and 5-13, Ref. 5.10) and the Waste Package Plan (pp.3-15, 3-17, and 3-24, Ref. 5.9). The design data request addressed herein is: Characterize the preliminary 21 pressurized water reactor (PWR) advanced (A) uncanistered fuel (UCF) waste package (WP) to show that the design is feasible for use in the MGDS environment. The purpose of this analysis is to respond to a concern that the long-term disposal thermal issues for the UCF WP do not preclude UCF WP compatibility with the MGDS. The objective of this analysis is to provide thermal parameter information for the preliminary UCF WP design under nominal MGDS repository conditions. The results are intended to show that the design has a reasonable chance to meet the MGDS design requirements for normal MGDS operation and to provide the required guidance to determining the major design issues for future design efforts. Future design efforts will focus on UCF design changes as further design and operations information becomes available.

Objectives of this program are to provide an improved thermal barrier system with increased temperature capability and reliability relative to current systems. This report describes the bond coat development and deposition, manufacturing, and repair.

Three runs were carried out in the continuous stirred autoclave reactor with Englehard Zn-0312 T 1/8 {open_quotes}zinc chromite{close_quotes} catalyst and with decahydronaphthalene (Decalin{reg_sign}) as the slurry liquid. One short run, which was prematurely terminated by operational problems, was designed to define the effect of stirrer speed on catalyst performance. Two longer runs completed the data base required for kinetic characterization of the unpromoted {open_quotes}zinc chromite{close_quotes} catalyst. Although analysis of the data is not complete, it is evident that: (1) stirrer speed has no significant effect on the measured reaction rate, and; (2) carbon dioxide appears to inhibit catalyst activity.

In this paper, a time-dependent engine model is used for predicting hydrogen engine efficiency and emissions. The model uses basic thermodynamic equations for the compression and expansion processes, along with an empirical correlation for heat transfer, to predict engine indicated efficiency. A friction correlation and a supercharger/turbocharger model are then used to calculate brake thermal efficiency. The model is validated with many experimental points obtained in a recent evaluation of a hydrogen research engine. A The validated engine model is then used to calculate fuel economy and emissions for three hydrogen-fueled vehicles: a conventional, a parallel hybrid, and a series hybrid. All vehicles use liquid hydrogen as a fuel. The hybrid vehicles use a flywheel for energy storage. Comparable ultra capacitor or battery energy storage performance would give similar results. This paper analyzes the engine and flywheel sizing requirements for obtaining a desired level of performance. The results indicate that hydrogen lean-burn spark-ignited engines can provide a high fuel economy and Equivalent Zero Emission Vehicle (EZEV) levels in the three vehicle configurations being analyzed.

The report provides a synopsis of the FY94/95 Thermal Stabilization Campaign. The FY94 Thermal Stabilization Campaign ran from November 1, 1994 to June 13, 1995 and stabilized 236 items (22 kg) of reactive plutonium bearing material. A total of 49 cans of stabilized material was moved to the vaults for interim storage. While the initial downtime was high, with an Operating Efficiency (OE) of 27% over the first 3 months, the OE improved to 78% during the last 5 months for an overall DE of 58%. The campaign was completed 85 days ahead of schedule thus exceeding the ``Excellent``date for the Performance Base Incentive (PBI) for this campaign by 25 business days.

By studying pressure fluctuations using a system identification approach, it is hypothesized that circulating fluidized bed (CFB) pressure fluctuations are indicative of CFB hydrodynamics in two ways. First, the frequency phenomenon that is observed in the lower regions of the CFB under conditions of high solids loading is the result of lower dense bed voidage oscillations. Our results suggest that a surface wave phenomena inversely proportional to the square root of the bed diameter is also be observed in CFB pressure fluctuations under most conditions. By matching revised similitude parameters between two CFBs a number of conclusions can be drawn. First, spectral analysis of pressure fluctuations, if properly applied, can be used to verify that similitude has been achieved. To do this, not only must the Bode plot characteristics important for hydrodynamics be identified, but the pressure fluctuation structure at all elevations of the CFB must be similar. The set of similitude parameters defined by Glicksman is not sufficient to establish hydrodynamic similitude. The solids flux as typically measured in the downcomer does not contain information on the solids hold-up in the riser, or the amount of solids that progress downwards in the annulus rather than exit the riser. It …

The pressure fluctuations in the transition regime between bubbling fluidization and fast fluidization were investigated using system identification techniques. The results show that the voidage waves and surface eruption effects seen in bubbling fluidized beds are also observed in the transition regime fluctuations. In addition, a third frequency phenomenon is observed in the spectrum which is hypothesized to be a surface wave phenomenon analogous to surface waves in water. The validity of previously derived similitude parameters for bubbling fluidized beds (BFB) was investigated using spectral analysis of pressure fluctuations. When BFB similitude parameters are matched in two different beds, the pressure dynamics are similar under most conditions, suggesting that the correct similitude parameters have been defined for BFBs.

Quality of life as a concept has been used in many ways in the public policy arena. It can be used in summative evaluations to assess the impacts of policies or programs. Alternatively, it can be applied to formative evaluations to provide input to the formation of new policies. In short, it provides the context for the understanding needed to evaluate the results of choices that have been made in the public policy arena, or the potential of choices yet to be made. In either case, the public policy question revolves around the positive or negative impact the choice will have on quality of life, and the magnitude of that impact. This discussion will develop a conceptual framework that proposes that an assessment of quality of life is based on a comparison of expectations with experience. The framework defines four basic components from which these expectations arise: natural conditions, social conditions, the body, and the mind. Each one of these components is generally described, and associated with a general policy or rhetorical category which gives it its policy vocabulary--environmental quality, economic well-being, human health, and self-fulfillment.

This notice of construction (NOC) provides information regarding the source and the estimated quantity of potential airborne radionuclide emissions resulting from the operation of the Hot Conditioning System (HCS) Annex. The construction of the HCS Annex is scheduled to conunence on or about December 1996, and will be completed when the process equipment begins operations. This document serves as a NOC pursuant to the requirements of 40 Code of Federal Regulations (CFR) 61 for the HCS Annex. About 80 percent of the U.S. Department of Energy`s spent nuclear fuel (SNF) inventory is stored under water in the Hanford Site K Basins. Spent nuclear fuel in the K West Basin is contained in closed canisters, while the SNF in the K East Basin is contained in open canisters, which allows release of corrosion products to the K East Basin water. Storage of the current inventory in the K Basins was originally intended to be on an as-needed basis to sustain operation of the N Reactor while the Plutonium-Uranium Extraction (PUREX) Plant was refurbished and restarted. The decision in December 1992 to deactivate the PUREX Plant left approximately 2, 1 00 MT (2,300 tons) of uranium, as part of 1133 N Reactor …

Modicon Compact Programmable Logic Controller (PLC). The device configuration integrates the isolation and current-carrying capacities of mechanical relays with the logic and programming sophistication of the PLC. This document provides descriptions of components and tasks involved in the PLC system for controlling and monitoring the FGTEI. All control functions required by the PLC, and how they are implemented, are described in detail.

Results on {tau} physics at SLD are presented. They are based on 4,316 {tau}-pair events selected from a 150 k Z{sup 0} data sample collected at the SLC. These results include measurements of the {tau} lifetime ({tau}{sub r} = 288.1 {+-} 6.1 {+-} 3.3 fs), the {tau} Michel parameters ({rho} = 0.71 {+-} 0.09 {+-} 0.04, {zeta} = 1.03 {+-} 0.36 {+-} 0.05, and {zeta}{delta} = 0.84 {+-} 0.27 {+-} 0.05), and the {tau} neutrino helicity (h{sub {nu}} = {minus}0.81 {+-} 0.18 {+-} 0.03).

The 241-AW Tank Farm, located in the 200 East Area of the Hanford Site, contains six 1.16 Mgal double-shell tanks. The tanks are used primarily for storage of waste from facilities such as PUREX and B Plant. Tanks 102-AW and 106-AW commonly are used for staging waste concentrated by the evaporator.

If quarks are composite particles then excited states are expected. We estimate the discovery mass reach as a function of integrated luminosity for excited quarks decaying to dijets at the Tevatron the mass reach is 0.94 TeV for Run 11 (2 fb{sup -1}) and 1. 1 TeV for TeV33 (30 fb{sup -1}). At the LHC the mass reach is 6.3 TeV for 100 fb{sup -1}. At a VLHC with a center of mass energy {radical}s, of 50 TeV (200 TeV) the mass reach is 25 TeV (78 TeV) for an integrated luminosity of 10{sup 4} fb{sup -1}. However, an excited quark with a mass of 25 TeV would be discovered at a hadron collider with {radical}s = 100 TeV and an integrated luminosity of 13 fb{sup -1}, illustrating a physics example where a factor of 2 in machine energy is worth a factor of 1000 in luminosity.

A new repository waste package (WP) concept for spent nuclear fuel (SNF) is being investigated that uses depleted uranium (DU) to improve performance and reduce the uncertainties of geological disposal of SNF. The WP would be filled with SNF and then filled with depleted uranium (DU) ({approximately}0.2 wt % {sup 235}U) dioxide (UO{sub 2}) or DU silicate-glass beads. Fission products and actinides can not escape the SNF UO{sub 2} crystals until the UO{sub 2} dissolves or is transformed into other chemical species. After WP failure, the DU fill material slows dissolution by three mechanisms: (1) saturation of AT groundwater with DU and suppression of SNF dissolution, (2) maintenance of chemically reducing conditions in the WP that minimize SNF solubility by sacrificial oxidation of DU from the +4 valence state, and (3) evolution of DU to lower-density hydrated uranium silicates. The fill expansion seals the WP from water flow. The DU also isotopically exchanges with SNF uranium as the SNF degrades to reduce long-term nuclear-criticality concerns.

Document provides the results of tests done on Product Cans from the HC-21C sludge stabilization process. Tests included running a simulated Thermogravimetric Analysis, TGA, on the processed material that have received Loss On Ignition (LOI) sample results that show a gain on ignition or a high LOI and reprocessing product cans with high LOIs. Also, boat material temperatures in the furnace were tracked during the testing.

This document provides the test plan and test specification for SNF cold vacuum drying proof of concept, CVD process equipment validation, and proof of performance testing.

The US Department of Energy (DOE) must provide a demonstration of compliance with the final US Environmental Protection Agency (EPA) ground water protection standards for inactive mill sites pursuant to 40 CFR Part 192. This plan outlines the proposed strategy to demonstrate compliance with the ground water standards at the Maybell, Colorado, Uranium Mill Tailings Remedial Action (UMTRA) Project site. This demonstration consists of (1) the ground water protection standard, (2) a performance assessment, (3) a closure performance demonstration, and (4) a performance monitoring and corrective action program.

The Savannah River Technology Center is evaluating new field sampling methodologies to more easily determine concentrations of radionuclides in aqueous systems. One methodology studied makes use of 3M EmporeTM disks. The disks are composed of selective resins embedded in a Teflon support. The disks remove the ion of interest from aqueous solutions when the solution is passed through the disk. The disk can then be counted directly to quantify the isotope of interest. Four types of disks were studied during this work: for the extraction of technetium (two types), cesium, plutonium, and strontium. A sampler has been developed for automated, unattended, in situ use of the EmporeTM disks.