Heat flow from internal and external sources and the environment create machine deformations, resulting in positioning errors between the tool and workpiece. There is no industrially accepted method for thermal error compensation. A simple model has been selected that linearly relates discrete temperature measurements to the deflection. The biggest problem is how to locate the temperature sensors and to determine the number of required temperature sensors. This research develops a method to determine the number and location of temperature measurements.

This report is on Legislative Research in Congressional Offices: A Primer.

During fiscal year 1996, the Department of Energy`s Office of Fissile Materials Disposition (OFMD) funded Los Alamos National Laboratory (LANL) to investigate issues associated with the fabrication of plutonium from dismantled weapons into mixed-oxide (MOX) nuclear fuel for disposition in nuclear power reactors. These issues can be divided into two main categories: issues associated with the fact that the plutonium from dismantled weapons contains gallium, and issues associated with the unique characteristics of the PuO{sub 2} produced by the dry conversion process that OFMD is proposing to convert the weapons material. Initial descriptions of the experimental work performed in fiscal year 1996 to address these issues can be found in Nuclear Fuels Technologies Fiscal Year 1996 Research and Development Test Matrices`. However, in some instances the change in programmatic emphasis towards the Parallex program either altered the manner in which some of these experiments were performed (i.e., the work was done as part of the Parallex fabrication development and not as individual separate-effects tests as originally envisioned) or delayed the experiments into Fiscal Year 1997. This report reviews the experiments that were conducted and presents the results. 7 figs., 14 tabs.

This eighth quarterly report summarizes activity from July 1, 1996 through September 30, 1996. The report is organized in sections describing background information and work performed under the main work breakdown structure (WBS) categories. The WBS categories included are fuel processor, fuel cell stack, and system integration and controls. Program scheduling and task progress are presented in the appendix.

In direct drive ICF, nonuniformities in laser illumination seed ripples at the ablation front in a process called imprint. These non nonuniformities grow during the capsule implosion and, if initially large enough, can penetrate the capsule shell, impede ignition, or degrade burn. Imprint has been simulated for recent experiments performed on the Nova laser at LLNL examining a variety of beam smoothing conditions. Most used laser intensities similar to the early part of an ignition capsule pulse shape, I=10X13 W/cm3. The simulations matched most of the measurements of imprint modulation. The effect of imprint upon National Ignition Facility (NIF) direct drive ignition capsules has also been simulated. Imprint is predicted to give modulation comparable to an intrinsic surface finish of 10 nm RMS. Modulation growth was examined using the Haan model, with linear growth as a function of spherical harmonic mode number obtained from an analytic dispersion relation. Ablation front amplitudes are predicted to become substantially nonlinear, so that saturation corrections are large. Direct numerical simulations of two- dimensional multimode growth were also performed. The capsule shell is predicted to remain intact, which gives a basis for believing that ignition can be achieved.

A weekly publication, the Texas Register serves as the journal of state agency rulemaking for Texas. Information published in the Texas Register includes proposed, adopted, withdrawn and emergency rule actions, notices of state agency review of agency rules, governor's appointments, attorney general opinions, and miscellaneous documents such as requests for proposals. After adoption, these rulemaking actions are codified into the Texas Administrative Code.

The primary objective of this study was to provide recommendations for Mined Geologic Disposal System requirements affected by thermal loading that will provide sufficient definition to facilitate development of design concepts and support life cycle cost determinations. The study reevaluated and/or redefined selected thermal goals used for design and are currently contained in the requirements documents or the Controlled Design Assumption Document. The study provided recommendations as to what, if any, actions (such as edge loading and limiting of the heat variability between waste packages) are needed and must be accommodated in the design. Additionally, the study provided recommendations as to what alternative thermal loads should be maintained for continued flexibility. Section 1 provides the study objective, background, scope, and organization of the report. Section 2 documents the requirements and standards to include quality assurance (QA) requirements, any requirements used or evaluated, and the inputs and assumptions considered. Section 3 provides the analysis and recommendations for the thermal goals reevaluation. Section 4 discusses the evaluation of edge loading and provides conclusions. Section 5 provides the analyses done to establish recommendations as to what requirements need to be implemented to either limit or manage the amount of heat output variability that …

The primary objective of this study was to provide recommendations for Mined Geologic Disposal System requirements affected by thermal loading that will provide sufficient definition to facilitate development of design concepts and support life cycle cost determinations. The study reevaluated and/or redefined selected thermal goals used for design and are currently contained in the requirements documents or the Controlled Design Assumption Document. The study provided recommendations as to what, if any, actions (such as edge loading and limiting of the heat variability between waste packages) are needed and must be accommodated in the design. Additionally, the study provided recommendations as to what alternative thermal loads should be maintained for continued flexibility. This report contains seven appendices: Technical basis for evaluation of thermal goals below the potential nuclear was repository at Yucca Mountain; Thermal-mechanical evaluation of the 200 C drift-wall temperature goal; Evaluation of ground stability and support; Coupled ventilation and hydrothermal evaluations; Heat flow and temperature calculations for continuously ventilated emplacement drifts; Thermal management using aging and/or waste package selection; and Waste stream evaluations.

Experimental short pulse lasers are rapidly approaching energy levels where target irradiances exceeding 10{sup 20} W/CM{sup 2} are routinely achievable. These high intensity levels will open up a new class of solid target interaction physics where relativistic effects must be included and non-traditional absorption mechanisms become significant. However much remains to be understood of the absorption physics at lower intensities where classical absorption is dominated by collisional and resonance absorption. If attention is paid to producing clean laser pulses that do not significantly pre-pulse interact with the target, it is possible to produce plasmas of sufficiently short scale length that near-solid density interactions are observable at intensities exceeding 10{sup 18} W/CM{sup 2} for 100 fs laser irradiation. We report here extensions to our previous efforts at normal incidence that expand our observations to non-normal angles including the effect of polarization for several target materials. Between 10{sup 13} W/CM{sup 2} and 10{sup 14} W/CM{sup 2} we observe that the target absorption retains a signature of the intra-band atomic transitions. At higher intensities a more material independent ion-electron collisional absorption and short scale length resonance absorption dominate. P - polarized absorption in short scale length plasmas has been observed to exceed 60 …

The ground carbonized RDF slurry from the grinding trials at IKA Works at approximately 50 wt.% solids was sealed in drums and shipped to the Energy and Environmental Research Corporation (EER) for the dioxin/furan and trace heavy metal combustion tests. In addition, a fuel characterization and trace component analysis was completed for this final carbonized RDF slurry fuel. This final fuel was a blend of several fuels from the pilot scale slurry carbonization experiments. As can be seen from the data, the final carbonized RDF has an exceptional heating value and volatile matter content. In addition, trace components are significantly lower than the raw RDF pellets. The report summarizes results from combustion tests and air pollution monitoring of these tests. For the upcoming time period 10/96--01/97, it is anticipated that the analysis of the dioxin/furan and trace heavy metal combustion test will be completed. This analysis includes rheology and particle size distribution analysis of the carbonized RDF slurry fuel, carbon content and TCLP of the combustion ash, trace heavy metal balances around combustor, and dioxin/furan emissions. Finally, the slurry carbonization computer model and computer simulations will be completed in the next reporting period (including the waste water treatment subsystem). Based …

A field demonstration was funded by the US Department of Energy (DOE) to quantify the potential use of montan wax as a subsurface barrier material for nuclear waste management applications. As part of that demonstration, a study was completed to address some of the characteristics of the wax. Of particular interest is its resistance to chemical and structural changes that would influence its integrity as a barrier to minimize the migration of contaminants from their storage or disposal locations. Properties that were evaluated included hardness, melting point, molecular weight, and biodegradation as a function of gamma radiation dose. Based on the data obtained to date the wax is extremely resistant to radiation-induced change. Coupled with low permeability, the material shows promise as a subsurface barrier material.

One of the options for a design of a Central Solenoid in ITER and other tokamak machines is pancake would modules. In this configuration joints have to be placed in maximum magnetic field with high changing rate. In this condition joints should be designed to have at least the same or larger temperature margin as that for the conductor in the same field. It is argued that joints in parallel field can be designed to meet this requirement along with reasonably low DC resistance. Losses in parallel field are calculated and design features which can suppress AC losses without increasing DC resistance are discussed. Recommendations for low loss, low DC resistance joints are made.

In the conceptual design of the APT cooling water system, several options exist for the design of the system(s) which serve as the ultimate heat sink. This study will evaluate alternative methods of providing an ultimate heat sink to the APT.

The magnetic phase diagrams of all dilute Cr alloys can be explained by a simple theoretical model with coupled spin- and charge-density waves and a finite electron reservoir. If the charge-density wave and electron reservoir are sufficiently large, the paramagnetic to commensurate spin-density wave transition becomes strongly first order, as found in Cr{sub 1- x}Fe{sub x} and Cr{sub 1-x}Si{sub x} alloys. The observed discontinuity of the slope dT{sub N}/dx at the triple point and the bending of the CI phase boundary are also natural consequences of this model.

The purpose of this DOE guide is to facilitate the use of consistent procedures to document cost and performance information for projects involving the remediation of media contaminated with hazardous and radioactive wastes. It provides remedial action project managers with a standardized set of data to document completed remediation projects. Standardized reporting of data will broaden the utility of the information, increase confidence in the effectiveness of future remedial technologies, and enhance the organization, storage and retrieval of relevant information for future cleanup projects. The foundation for this guide was laid down by the Federal Remediation Technologies Roundtable (FRTR) in their publication, Guide to Documenting Cost and Performance for Remediation Projects, EPA-542-B- 95-002. Member agencies of the FRTR include the US EPA, the US DOD, the US DOE, and the US DOI. All the member agencies are involved in site remediation projects and anticipate following the guidance provided in the above reference. Therefore, there is much to be gained for DOE to be consistent with the other member agencies as it will be easier to compare projects across different agencies and also to learn from the experiences of a wider spectrum of prior completed projects.

This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Fire in Contaminated Area. The calculations needed to quantify the risk associated with this accident scenario are included within.

The new, rapidly evolving field of industrial ecology - the objective, multidisciplinary study of industrial and economic systems and their linkages with fundamental natural systems - provides strong ground for believing that a more environmentally and economically efficient economy will be more information intensive and complex. Information and intellectual capital will be substituted for the more traditional inputs of materials and energy in producing a desirable, yet sustainable, quality of life. While at this point this remains a strong hypothesis, the evolution of the automobile industry can be used to illustrate how such substitution may, in fact, already be occurring in an environmentally and economically critical sector.

The Westinghouse Hanford Company is exploring various options for retrieving waste materials from the underground storage tanks at the Hanford Site in Richland, Washington. One option under investigation is the use of a commercially available sluicing nozzle manufactured by Bristol Equipment Company.

This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term storage and long-term management of double-shell tank 241-AN-104.

This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term storage and long-term management at single-shell tank 241-U-102.

This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-AN-101. This report supports the requirements of Tri-Party Agreement Milestone M-44-09.

Testing was carried out with the cooperation of Westinghouse Hanford Company and the United States Bureau of Mines at the Pittsburgh Research Center in Pennsylvania under the Memorandum of Agreement 14- 09-0050-3666. Several core drilling equipment items, specifically those which can come in contact with flammable gasses while drilling into some waste tanks, were tested under conditions similar to actual field sampling conditions. Rotary drilling against steel and rock as well as drop testing of several different pieces of equipment in a flammable gas environment were the specific items addressed. The test items completed either caused no ignition of the gas mixture, or, after having hardware changes or drilling parameters modified, produced no ignition in repeat testing.

This paper describes the design and testing of critical gas turbine components. Development of catalytic combustors and diagnostic equipment is included.

Readout cables extend from the ladder end to the outer barrel radius in the region where the F-disks are mounted. In this region it is difficult to know what the gas temperature will be due to the power dissipating components on the F-disks and power from all the cables. This region is convectively cooled by the barrel bulkhead and the F-disk cooling channel. Power dissipated in the cable will not only warm the surrounding gas but will warm the hybrid to which it is attached on the ladders and disks. Just how much power goes into the hybrid will be estimated here. Physically, the cable is composed of two layers of copper which are separated and encased by 3 layers of kapton. The central kapton layer is 0.001-inch thick, the outer two kapton layers are 0.0005-inch thick, and the two copper layers are 0.0006-inch thick. Mike Matulik estimated the power dissipation of the cables for the 3. 6, and 9 chip ladders. These estimates are based on the assumed cross-sectional area of copper in the cable and the current these cables will carry, for a 12-inch cable length. The assumed powers are 14, 49, and 114 mW, respectively. The cable …