This quality assurance project plan (QAPjP) summarizes requirements used by Lockheed Martin Energy Systems, Incorporated (LMES) Development Division at Y-12 for conducting chemical reactivity testing of Department of Energy (DOE) owned spent nuclear fuel, sponsored by the National Spent Nuclear Fuel Program (NSNFP). The requirements are based on the NSNFP Statement of Work PRO-007 (Statement of Work for Laboratory Determination of Uranium Hydride Oxidation Reaction Kinetics.) This QAPjP will utilize the quality assurance program at Y-12, QA-101PD, revision 1, and existing implementing procedures for the most part in meeting the NSNFP Statement of Work PRO-007 requirements, exceptions will be noted.

The paper industry has long had a need to better understand and control its papermaking process upstream, specifically at the wet end in the forming section of a paper machine. A vision-based system is under development that addresses this need by automatically measuring and interpreting the pertinent paper web parameters at the wet end in real time. The wet-end characterization of the paper web by a vision system involves a four-dimensional measurement of the slurry in real time. These measurements include the two-dimensional spatial information, the intensity profile, and the depth profile. This paper describes the real-time depth profile measurement system for the high-speed moving slurry. A laser line-based measurement method is used with a high-speed programmable camera to directly measure slurry height. The camera is programmed with a profile algorithm, producing depth data at fast sampling rates. Analysis and experimentation have been conducted to optimize the system for the characteristics of the slurry and laser line image. On-line experimental results are presented.

In joining defects on semiconductor wafer maps into clusters, it is common for defects caused by different sources to overlap. Simple morphological image processing tends to either join too many unrelated defects together or not enough together. Expert semiconductor fabrication engineers have demonstrated that they can easily group clusters of defects from a common manufacturing problem source into a single signature. Capturing this thought process is ideally suited for fuzzy logic. A system of rules was developed to join disconnected clusters based on properties such as elongation, orientation, and distance. The clusters are evaluated on a pair-wise basis using the fuzzy rules and are joined or not joined based on a defuzzification and threshold. The system continuously re-evaluates the clusters under consideration as their fuzzy memberships change with each joining action. The fuzzy membership functions for each pair-wise feature, the techniques used to measure the features, and methods for improving the speed of the system are all developed. Examples of the process are shown using real-world semiconductor wafer maps obtained from chip manufacturers. The algorithm is utilized in the Spatial Signature Analyzer (SSA) software, a joint development project between Oak Ridge National Lab (ORNL) and SEMATECH.

The ability to manage large image databases has been a topic of growing research over the past several years. Imagery is being generated and maintained for a large variety of applications including remote sensing, art galleries, architectural and engineering design, geographic information systems, weather forecasting, medical diagnostics, and law enforcement. Content-based image retrieval (CBIR) represents a promising and cutting-edge technology that is being developed to address these needs. To date, little work has been accomplished to apply these technologies to the manufacturing environment. Imagery collected from manufacturing processes have unique characteristics that can be used in developing a manufacturing-specific CBIR approach. For example, a product image typically has an expected structure that can be characterized in terms of its redundancy, texture, geometry, or a mixture of these. Defect objects in product imagery share a number of common traits across product types and imaging modalities as well. For example, defects tend to be contiguous, randomly textured, irregularly shaped, and they disrupt the background and the expected pattern. We will present the initial results of the development of a new capability for manufacturing-specific CBIR that addresses defect analysis, product quality control, and process understanding in the manufacturing environment. Image data from the …

An array of epidemiological results and databases on test animal indicate that risk of cancer and atherosclerosis can be up- or down-regulated by diet through a range of 200%. Other factors contribute incrementally and include the natural terrestrial environment and various human activities that jointly produce complex exposures to endotoxin-producing microorganisms, ionizing radiations, and chemicals. Ordinary personal habits and simple physical irritants have been demonstrated to affect the immune response and risk of disease. There tends to be poor statistical correlation of long-term risk with single agent exposures incurred throughout working careers. However, Agency recommendations for control of hazardous exposures to humans has been substance-specific instead of contextually realistic even though there is consistent evidence for common mechanisms of toxicological and carcinogenic action. That behavior seems to be best explained by molecular stresses from cellular oxygen metabolism and phagocytosis of antigenic invasion as well as breakdown of normal metabolic compounds associated with homeostatic- and injury-related renewal of cells. There is continually mounting evidence that marrow stroma, comprised largely of monocyte-macrophages and fibroblasts, is important to phagocytic and cytokinetic response, but the complex action of the immune process is difficult to infer from first-principle logic or biomarkers of toxic injury. The …

The Argonne concept for an accelerator complex for efficiently producing high-quality radioactive beams from ion source energy up to 6-15 MeV/u is described. The Isotope-Separator-On-Line (ISOL) method is used. A high-power driver accelerator produces radionuclides in a target that is closely coupled to an ion source and mass separator. By using a driver accelerator which can deliver a variety of beams and energies the radionuclide production mechanisms can be chosen to optimize yields for the species of interest. To effectively utilize the high beam power of the driver two-step target/ion source geometries are proposed (1) Neutron production with intermediate energy deuterons on a primary target to produce neutron-rich fission products in a secondary {sup 238}U target, and (2) Fragmentation of neutron-rich heavy ion rich fission products in a secondary beams such as {sup 18}O in a target/catcher geometry. Heavy ion beams with total energies in the 1-10 GcV range are also available for radionuclide production via high-energy spallation reactions. At the present time R and D is in progress to develop superconducting resonator structures for a driver linac to cover the energy range up to 100 MeV per nucleon for heavy ions and 200 MeV for protons. The post accelerator …

The Nash Draw Brushy Canyon Pool in Eddy County New Mexico is a cost-shared field demonstration project in the US Department of Energy Class II Program. A major goal of the Class III Program is to stimulate the use of advanced technologies to increase ultimate recovery from slope-basin clastic reservoirs. Advanced characterization techniques are being used at the Nash Draw project to develop reservoir management strategies for optimizing oil recovery from this Delaware reservoir. Analysis, interpretation, and integration of recently acquired geologic, geophysical, and engineering data revealed that the initial reservoir characterization was too simplistic to capture the critical features of this complex formation. Contrary to the initial characterization, a new reservoir description evolved that provided sufficient detail regarding the complexity of the Brushy Canyon interval at Nash Draw. This new reservoir description is being used as a risk reduction tool to identify ''sweet spots'' for a development drilling program as well as to evaluate pressure maintenance strategies. The reservoir characterization, geological modeling, 3-D seismic interpretation, and simulation studies have provided a detailed model of the Brushy Canyon zones. This model was used to predict the success of different reservoir management scenarios and to aid in determining the most favorable …

This report examines the feasibility of remediating ancillary equipment associated with the 241-AX Tank Farm at the Hanford Site. Ancillary equipment includes surface structures and equipment, process waste piping, ventilation components, wells, and pits, boxes, sumps, and tanks used to make waste transfers to/from the AX tanks and adjoining tank farms. Two remedial alternatives are considered: (1) excavation and removal of all ancillary equipment items, and (2) in-situ stabilization by grout filling, the 241-AX Tank Farm is being employed as a strawman in engineering studies evaluating clean and landfill closure options for Hanford single-shell tanks. This is one of several reports being prepared for use by the Hanford Tanks Initiative Project to explore potential closure options and to develop retrieval performance evaluation criteria for tank farms.

The Hanford Defined Waste (HDW) model (Rev. 4) (Agnew et al. 1997) projects inventories (as of January 1, 1994) of 46 radionuclides in the Hanford Site underground waste storage tanks. To model the distribution of the 46 radionuclides among the 177 tanks, it was necessary for Agnew et al. to estimate the solubility of each radionuclide in the various waste types originally added to the single-shell tanks. Previous editions of the HDW model used single-point solubility estimates. The work described in this report was undertaken to provide more accurate estimates of the solubility of all 46 radionuclides in the various wastes.

The application cyclic CO2, often referred to as the CO2 Huff-n-Puff process, may find its niche in the maturing waterfloods of the Permian Basin. Coupling the CO2 Huff-n-Puff process to miscible flooding applications could provide the needed revenue to sufficiently mitigate near-term negative cash flow concerns in capital-intensive miscible projects. Texaco Exploration and Production Inc. and the US Department of Energy have teamed up in a attempt to develop the CO2 Huff-n-Puff process in the Grayburg and San Andres formations which are light oil, shallow shelf carbonate reservoirs that exist throughout the Permian Basin. This cost-shared effort is intended to demonstrate the viability of this underutilized technology in a specific class of domestic reservoir.

High-heat producing sludge from tank 241-C-106 will be sluiced and transferred to tank 241-AY-102 beginning in October 1998. Safety analyses have postulated that after retrieval, the waste in 241-AY-102 may generate and retain unsafe levels of flammable gases (Noorani 1998, Pasamebmetoglu etal. 1997). Unsafe levels of retained gas are not expected, but cannot be ruled out because of the large uncertainty in the gas generation and retention rates. The Tank Waste Remediation System Basis for Interim Operation (Noorani 1998) identifies the need for a contingency plan to add void fraction monitoring to tank 241-AY-102 within 2 weeks of the identification of flammable gas buildup that would warrant monitoring. The Tank 241-C-106 Waste Retrieval Sluicing System Process Control Plan (Carothers et al. 1998) committed to providing a contingency plan for deployment of the void fraction instrument (VFI) in tank 241-AY-102. The VFI determines the local void fraction of the waste by compressing a waste sample captured in a gas-tight test chamber. The sample chamber is mounted on the end of a 76-cm (2.5-ft) arm that can be rotated from vertical to horizontal when the instrument is deployed. Once in the waste, the arm can be positioned horizontally and rotated to sample …

The Corrective Action Investigation Plan for Corrective Action Unit 266, Area 25 Building 3124 Leachfield, has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the U.S. Department of Energy, Nevada Operations Office; the State of Nevada Division of Environmental Protection; and the U.S. Department of Defense. Corrective Action Unit 266 consists of the Corrective Action Site 25-05-09 sanitary leachfield and associated collection system. This Corrective Action Investigation Plan is used in combination with the Work Plan for Leachfield Corrective Action Units: Nevada Test Site and Tonopah Test Range, Nevada (DOE/NV, 1998d). This Corrective Action Investigation Plan provides investigative details specific to Corrective Action Unit 266. Corrective Action Unit 266 is located southwest of Building 3124 which is located southwest and adjacent to Test Cell A. Test Cell A was operational during the 1960s to test nuclear rocket reactors in support of the Nuclear Rocket Development Station. Operations within Building 3124 from 1962 through the early 1990s resulted in effluent releases to the leachfield and associated collection system. The subsurface soils in the vicinity of the collection system and leachfield may have been impacted by effluent containing contaminants of potential concern generated …

This report describes the implementation of a coupled mechanical /heat transfer simulation using a Finite Element Interface (FEI). The FE1 is an abstraction layer, which lies between the application code and its linear solver libraries, controlling the set-up and solution of the linear system arising in the finite element simulation. The performance and scalability of the ISIS++ FE1 is examined on the ASCI Red and Blue machines in the context of the ALE3D finite element simulation code.

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This Double-Shell Tank Emergency Pumping Guide provides the preplanning necessary to expeditiously remove any waste that may leak from the primary tank to the secondary tank for Hanford's 28 DSTS. The strategy is described, applicable emergency procedures are referenced, and transfer routes and pumping equipment for each tank are identified.

This document contains the Hanford transmission and distribution system relay settings that are under the control of Electrical Utilities.

This engineering task plan identifies the activities required for developing an ultra high pressure water drill system for installation of a saltwell screen in Tank BY-105. A water drill system is needed to bore through the hard waste material in this tank because of the addition of Portland cement in the 1960s and/or 1970s. The activities identified in this plan include the design, procurement, and qualification testing of the water drill along with readiness preparations including developing operating procedures, training Operations personnel, and conducting an assessment of readiness.

Characterizing the waste in underground storage tanks at the Hanford Site is accomplished by obtaining a representative core sample for analysis. Core sampling is one of the numerous techniques that have been developed for use given the environmental and field conditions at the Hanford Site. Core sampling is currently accomplished using either Push Mode Core Sample Truck No.1 or; Rotary Mode Core Sample Trucks No.2, 3 or 4. Past analysis (WHC 1994) has indicated that the Core Sample Truck (CST) leveling jacks are structurally inadequate when lateral loads are applied. WHC 1994 identifies many areas where failure could occur. All these failures are based on exceeding the allowable stresses listed in the American Institute of Steel Construction (AISC) code. The mode of failure is for the outrigger attachments to the truck frame to fail resulting in dropping of the CST and possible overturning (Ref. Ziada and Hundal, 1996). Out of level deployment of the truck can exceed the code allowable stresses in the structure. Calculations have been performed to establish limits for maintaining the truck level when lifting. The calculations and the associated limits are included in appendix A. The need for future operations of the CSTS is limited. Sampling …

The Experimental Breeder Reactor II (EBR-II) at Argonne National Laboratory (ANL) West in Idaho is currently undergoing a plant closing operation, and a number of technical issues need to be addressed. This paper is related to the heat transfer analysis support effort performed for the upcoming draining operation of the primary sodium from the primary system tank. The issue addressed was how much of heat input would be required to the sodium if it were to be maintained in the liquid state during the prolonged period of the draining operation. The fluid dynamics analysis package FIDAP Code of Fluent Incorporated was used to model the primary tank system. It was possible to obtain solutions to the model in most of the cases considered, which provided the needed information for the project. However, certain appropriate choices of the solution algorithms were necessary in certain cases and in addition certain special measures had to be followed in order to successfully utilize the solution. In certain other instances, only some entirely different algorithm was the only successful choice, while in some other limited instances none of the algorithms or the special measures that were satisfactory for the earlier cases proved successful. Several configurations …

In accordance with DOE Order 5480.7A, Fire Protection, a Fire Hazards Analysis must be performed for all new facilities. LMHC Fire Protection has reviewed and approved the significant documentation leading up to the LDUA operation. This includes, but is not limited to, development criteria and drawings, Engineering Task Plan, Quality Assurance Program Plan, and Safety Program Plan. LMHC has provided an appropriate level of fire protection for this activity as documented.

Recommendation 93-5 Implementation Plan, Milestone 5,6.3.1.i requires issuance of this report which addresses ''updates to the tank contents model''. This report summarizes the review of the Hanford Defined Waste, Revision 4, model limitations and provides conclusions and recommendations for potential updates to the model.

The mission of the Hanford Fire Department (HFD) is to support the safe and timely cleanup of the Hanford site by providing a full range of services at the lowest possible cost to customers. These services include fire suppression, fire prevention, emergency rescue, emergency medical service, and hazardous materials response; and to be capable of dealing with and terminating emergency situations which could threaten the operations, employees, the general public, or interest of the U. S. Department of Energy operated Hanford Site. This includes response to surrounding fire departments/districts under mutual aid and state mobilization agreements and fire fighting, hazardous materials, and ambulance support to Washington Public Power Supply System (Supply System) and various commercial entities operating on site through Requests for Service from DOE-RL. The fire department also provides site fire marshal overview authority, fire system testing and maintenance, respiratory protection services, building tours and inspections, ignitable and reactive waste site inspections, prefire planning, and employee fire prevention education.

In 1998 Waste Management Federal Services of Hanford, Inc. began the integration of all low-level waste, mixed waste, and TRU waste-generating activities across the Hanford site. With seven contractors, dozens of generating units, and hundreds of waste streams, integration was necessary to provide acute waste forecasting and planning for future treatment activities. This integration effort provides disposition maps that account for waste from generation, through processing, treatment and final waste disposal. The integration effort covers generating facilities from the present through the life-cycle, including transition and deactivation. The effort is patterned after the very successful DOE Complex EM Integration effort. Although still in the preliminary stages, the comprehensive onsite integration effort has already reaped benefits. These include identifying significant waste streams that had not been forecast, identifying opportunities for consolidating activities and services to accelerate schedule or save money; and identifying waste streams which currently have no path forward in the planning baseline. Consolidation/integration of planned activities may also provide opportunities for pollution prevention and/or avoidance of secondary waste generation. A workshop was held to review the waste disposition maps, and to identify opportunities with potential cost or schedule savings. Another workshop may be held to follow up on some …

The purpose of this project was to develop a high peak power laser system (100 TW) and begin initial high intensity experiments that exploit its short pulse width (30 fs) and high repetition rate (1 - 10 Hz). Such a laser system presents unique capabilities such as permitting ultrafast time-resolved plasma physics experiments by probing the plasma with the 30 fs laser pulse. The high repetition rate also allows detailed, systematic studies of phenomena, not possible with large, single shot laser systems. During the previous year we have made good progress on the development of the laser. We have demonstrated the production of pulses up to the 5 TW level at 10 Hz and have installed an additional amplifier to take the system to 20 TW. We have pulse compressed the pulses to 30 fs and have developed a number of diagnostics to characterize the laser prepulse. During this year we have also activated a target chamber to begin plasma physics experiments in gas jet targets.