The versatile dot matrix printer of the DECwriter II was modified to enable printing of symbol characters., e.g., Greek letters and other symbol for mathematical expressions and units of measurement. This development involved the replacement of the read-only memory (ROM) units with erasable-programmable read-only memory (EPROM) units.

The objective of this research is to evaluate the melting behavior of Macrobatch 3 (MB3) for the Defense Waste Processing Facility (DWPF). This study focuses on the manipulation of the frit composition in order to enhance the melting rate of MB3, without sacrificing the quality of the final glass form. The goal is to find the proper frit composition so the development of this insulating layer is averted.

This report discusses results of testing done in the Savannah River Laboratory half tank and full tank mockup facilities using kaolin clay slurries and the relationship between cleaning radius and pump and slurry characteristics.

WSRC conducted a site selection study to identify, assess, and rank candidate sites for an onsite concrete batch plant at the Savannah River Site in the vicinity of F-Area.

The National Renewable Energy Laboratory's National Wind Technology Center (NWTC) has refocused its wind turbine design-code comparison effort to verify FAST{_}AD with ADAMS. FAST{_}AD is a wind turbine structural-response code developed by Oregon State University for the NWTC. ADAMS is a commercial, general-purpose, multibody-dynamics code developed by Mechanical Dynamics, Inc. ADAMS, which is used in many industries, has been rigorously tested. Both ADAMS and FAST{_}AD use the AeroDyn subroutine package for calculating aerodynamic forces. The University of Utah developed AeroDyn for the NWTC. To compare FAST{_}AD to ADAMS, we modeled a rough approximation of the AWT-27 P4 turbine, using the same properties for both simulators. The AWT-27 is a 275-kilowatt (kW), two-bladed wind turbine. We also created three-bladed versions of the turbine models to verify FAST{_}AD for three-bladed turbines. In this paper, we list the aerodynamic features used in the comparison. We also explain how the programs model the turbine structure, describe the degrees of freedom (DOFs) used for this study, and present simulation comparisons that show very good agreement.

We present a preliminary measurement of the central inclusive jet cross section using a successive combination algorithm based on relative transverse momenta (k{perpendicular}) for jet reconstruction. We analyze a 87.3 pb{sup -1} data sample collected by the D0 detector at the Fermilab Tevatron p{bar p} Collider during 1994-1995. The cross section, reported as a function of transverse momentum (p{sub T} > 60 GeV) in the central region of pseudo-rapidity (|{eta}| < 0.5), is in reasonable agreement with next-to-leading order QCD predictions. This is the first jet production measurement in a hadron collider using a successive combination type of jet algorithm.

As part of the Hanford River Protection Project (RPP), the Savannah River Technology Center (SRTC) has conducted tests on the pretreatment and vitrification of a radioactive waste sample from Hanford Tank 241-AZ-102. The original, AZ-102 sample which was received at SRTC was characterized and filtered to remove entrained solids.1 The sample was then passed sequentially through ion exchange columns containing SuperLig{reg_sign} 644 and 639 resins for the removal of cesium and technetium ions (Tc removed as pertechnetate, TcO{sub 4}{sup {minus}}), respectively.2 The cesium and technetium absorbed to the resins was then eluted to give separate eluate solutions containing relatively high concentrations of Cs{sup +} and TcO{sub 4}{sup {minus}}. According to the current plant design, the decontaminated Tank 241-AZ-102 sample and the eluate solutions will be subjected to separate evaporation and vitrification processes to give low- and high-activity waste glasses, respectively. This report describes evaporation testing of the Tc eluate solution derived from ion exchange processing of the Tank 241-AZ-102 sample with SuperLig 639 resin.

Compact high flux neutron generators are developed at the Lawrence Berkeley National Laboratory. The neutron production is based on D-D or D-T reaction. The deuterium or tritium ions are produced from plasma using either a 2 MHz or 13.56 MHz radio frequency (RF) discharge. RF-discharge yields high fraction of atomic species in the beam which enables higher neutron output. In the first tube design, the ion beam is formed using a multiple hole accelerator column. The beam is accelerated to energy of 80 keV by means of a three-electrode extraction system. The ion beam then impinges on a titanium target where either the 2.4 MeV D-D or 14 MeV D-T neutrons are generated. The MCNP computation code has predicted a neutron flux of {approximately}10{sup 11} n/s for the D-D reaction at beam intensity of 1.5 A at 150 kV. The neutron flux measurements of this tube design will be presented. Recently new compact high flux tubes are being developed which can be used for various applications. These tubes also utilize RF-discharge for plasma generation. The design of these tubes and the first measurements will be discussed in this presentation.

Noise measurements on CdZnTe detectors show that the main sources of detector-related noise are shot noise due to bulk leakage current and 1/f noise due to the detector surfaces. The magnitude of surface leakage current appears to have little or no effect on the detector noise. Measurements on guard-ring devices fabricated using gold-evaporated contacts show that the contacts behave as Schottky barriers, and the bulk current at typical operating voltages is likely dependent on the contact properties rather than directly on the material's bulk resistivity. This also suggests that the level of shot noise is affected by the detector contacts and not necessarily by the material's bulk resistivity. A significant reduction in the noise of coplanar-grid detectors has been obtained using a modified contact fabrication process.

The design of the newly installed medium-{beta} insert of the Fermilab Recycler Ring is presented. The design philosophy is outlined. The stringent optical and physical constraints, as well as their influence on the design, are discussed. The impact of the medium-{beta} insert on the Recycler Ring is shown. Engineering design and installation of the new insert is presented.

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Experiments have shown that the presence of a thin native oxide layer on the surface of a strained SiGe epilayer causes an order of magnitude increase in dislocation velocities during annealing over those observed in atomically clean samples and during crystal growth. This behavior is explained herein by stress-assisted dislocation kink nucleation at the oxide/epilayer interface. Finite element models are used to estimate the magnitude of stress local to steps at this interface due to both intrinsic and thermal expansion stresses, and dislocation theory is used to determine the resulting increase in single kink nucleation.

This is a multiyear experimental research program focused on improving relevant material properties of high-T{sub c} superconductors (HTSs) and on development of fabrication methods that can be transferred to industry for production of commercial conductors. The development of teaming relationships through agreements with industrial partners is a key element of the Argonne National Laboratory (ANL) program. Recent results are presented on YBa{sub 2}Cu{sub 3}O{sub x} (Y-123) coated conductors, including fabrication by pulsed laser deposition (PLD) and sol-gel techniques. An approach to understanding the critical current density (J{sub c}) of grain boundaries is also presented and a technique is identified for increasing J{sub c}.

An Envelope D Tank 241-C-106 sample was characterized for solids, elemental, and radioactive isotope content. The work was done by the Savannah River Technology Center (SRTC) to support the Hanford River Protection Project (RPP). The sludge from Hanford Tank 241-C-106 is high level waste that is to be included in the first ten years of processing by the RPP Waste Treatment Plant (WTP). The sample was a composite of caustic-leached and washed sludge from previous work at the Pacific Northwest National Lab (PNNL). Sludge analysis results were found to compare well with those of previous researchers analyzing leached samples from Tank 241-C-106. Composition of the liquid accompanying the sample was also measured.

This paper seeks to begin a discussion with regard to developing standardized Computer Aided Control System Design (CACSD) tools that are typically utilized in an undergraduate controls laboratory. The advocated CACSD design tools are based on the popular, commercially available MATLAB environment, the Simulink toolbox, and the Real-Time Workshop toolbox. The primary advantages of the proposed approach are as follows: (1) the required computer hardware is low cost, (2) commercially available plants from different manufacturers can be supported under the same CACSD environment with no hardware modifications, (3) both the Windows and Linux operating systems can be supported via the MATLAB based Real-Time Windows Target and the Quality Real Time Systems (QRTS) based Real-Time Linux Target, and (4) the Simulink block diagram approach can be utilized to prototype control strategies; thereby, eliminating the need for low level programming skills. It is believed that the above advantages related to standardization of the CACSD design tools will facilitate: (1) the sharing of laboratory resources within each university (i.e., between departments) and (2) the development of Internet laboratory experiences for students (i.e., between universities).

The Product Composition Control System (PCCS) is used to determine the acceptability of each batch of Defense Waste Processing Facility (DWPF) melter feed in the Slurry Mix Evaporator (SME). This control system imposes several constraints on the composition of the contents of the SME to define acceptability. These constraints relate process or product properties to composition via prediction models. A SME batch is deemed acceptable if its sample composition measurements lead to acceptable property predictions after accounting for modeling, measurement and analytic uncertainties. The baseline document guiding the use of these data and models is ''SME Acceptability Determination for DWPF Process Control (U)'' by Brown and Postles [1996]. A minimum of three PCCS constraints support the prediction of the glass durability from a given SME batch. The Savannah River Technology Center (SRTC) is reviewing all of the PCCS constraints associated with durability. The purpose of this review is to revisit these constraints in light of the additional knowledge gained since the beginning of radioactive operations at DWPF and to identify any supplemental studies needed to amplify this knowledge so that redundant or overly conservative constraints can be eliminated or replaced by more appropriate constraints.

The objective of this project is to develop an improved ultra-lightweigh cement using ultralight hollow glass spheres (ULHS). Work reported herein addresses Task 1: Assess Ultra-Lightweight Cementing Problems, Task 2: Review Russian Ultra-Lightweight Cement Literature, and Task 3: Test Ultra-Lightweight Cements. Results reported this quarter include a review and summary surface pipe and intermediate casing cementing conditions historically encountered in the US and establishment of average design conditions for ULHS cements. Russian literature concerning development and use of ultra-lightweight cements employing either nitrogen or ULHS was reviewed, and a summary is presented. Quality control testing of materials used to formulate ULHS cements in the laboratory was conducted to establish baseline material performance standards. A testing protocol was developed employing standard procedures as well as procedures tailored to evaluate ULHS. This protocol is presented and discussed. finally, results of initial testing of ULHS cements is presented along with analysis to establish cement performance design criteria to be used during the remainder of the project.

We point out what we may learn from the investigation of identical two-particle interferometry in ultrarelativistic heavy ion collisions if we assume a particular model scenario by the formation of a thermalized quark-gluon plasma hadronizing via a first-order phase transition to an interacting hadron gas. The bulk properties of the two-pion correlation functions are dominated by these late and soft resonance gas rescattering processes. However, we show that kaons at large transverse momenta have several advantages and a bigger sensitivity to the QCD phase transition parameters.

The overall objective of this project is the three phase development of an Early Entrance Coproduction Plant (EECP) which produces at least one product from at least two of the following three categories: (1) electric power (or heat), (2) fuels, and (3) chemicals. The objective is to have these products produced by technologies capable of using synthesis gas derived from coal and/or other carbonaceous feedstocks. The objective of Phase I is to determine the feasibility and define the concept for the EECP located at a specific site and to develop a Research, Development, and Testing Plan (RD and T) for implementation in Phase II. The objective of Phase II is to implement the RD and T as outlined in the Phase I RD and T Plan to enhance the development and commercial acceptance of coproduction technology that produces high-value products, particularly those that are critical to our domestic fuel and power requirements. The project will resolve critical knowledge and technology gaps on the integration of gasification and downstream processing to coproduce some combination of power, fuels, and chemicals from coal and/or other carbonaceous feedstocks. The objective of Phase III is to develop an engineering design package and a financing plan …

Ion exchange tests have been completed at the Savannah River Technology Center for British Nuclear Fuels Limited, Inc. as part of the Hanford River Protection Project. Radioactive cesium and technetium (pertechnetate form only) were removed by ion exchange from a sample of Envelope C salt solution from Hanford Tank 241-AN-102 (sample volume: approximately 17 L at 4.8 M Na plus). The original sample was diluted and subjected to strontium/transuranics (Sr/TRU) precipitation and filtration processes before ion exchange processing was performed. Batch contact and column tests for the ion exchange removal of cesium and technetium were then completed on the Sr/TRU-decontaminated product. Previous ion exchange tests were conducted on a smaller portion (0.5 L) of the Tank 241-AN-102 supernate sample, which had been similarly pretreated, and the results were reported in a separate document.

The overall objective of this work is to develop preliminary operating data including expected concentration endpoints using a C waste envelope simulant. The data is to be used for the preliminary Hanford RPP flow sheet development and LAW Melter Feed Evaporator design.

Instability flaw lengths were estimated for high level waste Tank 6 at its current fill height of 244 inches with an average specific gravity of 1.1. The instability flaw lengths were obtained by interpolation of the results from previous stress and fracture analyses for Type I high level waste tanks.

This document compiles information on the drilling and construction, well development, pump installation, and sediment and groundwater sampling applicable to the installation of five new RCRA wells in calendar year 2000 - 2001 at WMA TX-TY. Appendix A contains the Well Summary Sheets (as-built diagrams), the Well Construction Summary Reports, and the geologist's logs; Appendix B contains physical properties data; and Appendix C contains the borehole geophysical logs.

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