This report presents a five year plan for the laboratory. This plan takes advantage of the technical strengths of the lab and its staff to address issues of concern to the nation on a scope much broader than Sandia`s original mission, while maintaining the general integrity of the laboratory. The plan proposes initiatives in a number of technologies which overlap the needs of its customers and the strengths of its staff. They include: advanced manufacturing technology; electronics; information and computational technology; transportation energy technology and infrastructure; environmental technology; energy research and technology development; biomedical systems engineering; and post-cold war defense imperatives.

A team of senior managers from across the US Nuclear Regulatory Commission (NRC), working with the Office of Information Resources Management (IRM), has completed an NRC Strategic Information Technology (IT) Plan. The Plan addresses three major areas: (1) IT Program Management, (2) IT Infrastructure, and (3) Information and Applications Management. Key recommendations call for accelerating the replacement of Agency workstations, implementing a new document management system, applying business process reengineering to selected Agency work processes, and establishing an Information Technology Council to advise the Director of IRM.

The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels.

Dissolution experiments were performed on actual samples of NWCF Run H-4 radioactive calcine in fiscal years 1998 and 1999. Run H-4 is an aluminum/sodium blend calcine. Typical dissolution data indicates that between 90-95 wt% of H-4 calcine can be dissolved using 1gram of calcine per 10 mLs of 5-8M nitric acid at boiling temperature. Two liquid raffinate solutions composed of a WM-188/aluminum nitrate blend and a WM-185/aluminum nitrate blend were converted into calcine at the NWCF. Calcine made from each blend was collected and transferred to RAL for dissolution studies. The WM-188/aluminum nitrate blend calcine was dissolved with resultant solutions used as feed material for separation treatment experimentation. The WM-185/aluminum nitrate blend calcine dissolution testing was performed to determine compositional analyses of the dissolved solution and generate UDS for solid/liquid separation experiments. Analytical fusion techniques were then used to determine compositions of the solid calcine and UDS from dissolution. The results from each of these analyses were used to calculate elemental material balances around the dissolution process, validating the experimental data. This report contains all experimental data from dissolution experiments performed using both calcine blends.

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The Core Capability and Technical Enhancement (CC&TE) Program, a part of the Verification, Validation, and Engineering Assessment Program, was implemented to enhance and augment the technical capabilities of the Idaho National Engineering and Environmental Laboratory (INEEL). The purpose for strengthening the technical capabilities of the INEEL is to provide the technical base to serve effectively as the Environmental Management Laboratory for the Office of Environmental Management (EM). An analysis of EM's science and technology needs as well as the technology investments currently being made by EM across the complex was used to formulate a portfolio of research activities designed to address EM's needs without overlapping work being done elsewhere. An additional purpose is to enhance and maintain the technical capabilities and research infrastructure at the INEEL. This is a progress report for fiscal year 1998 for the five CC&TE research investment areas: (a) transport aspects of selective mass transport agents, (b) chemistry of environmental surfaces, (c) materials dynamics, (d) characterization science, and (e) computational simulation of mechanical and chemical systems. In addition to the five purely technical research areas, this report deals with the science and technology foundations element of the CC&TE from the standpoint of program management and complex-wide …

The purpose of LDRD #2349, Characterize and Model Final Waste Formulations and Offgas Solids from Thermal Treatment Processes, was to develop a set of tools that would allow the user to, based on the chemical composition of a waste stream to be immobilized, predict the durability (leach behavior) of the final waste form and the phase assemblages present in the final waste form. The objectives of the project were: • investigation, testing and selection of thermochemical code • development of auxiliary thermochemical database • synthesis of materials for leach testing • collection of leach data • using leach data for leach model development • thermochemical modeling The progress toward completion of these objectives and a discussion of work that needs to be completed to arrive at a logical finishing point for this project will be presented.

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The Tanks Focus Area (TFA) Multiyear Program Plan (MYPP) presents the recommended TFA technical program. The recommendation covers a 3-year funding outlook (FY96-FY98), with an emphasis on FY96 and FY97. In addition to defining the recommended program, this document also describes the processes used to develop the program, the implementation strategy for the program, the references used to write this report, data on the U.S. Department of Energy (DOE) tank site baselines, details on baseline assumptions and the technical elements, and a glossary.

This is an internal DOE Geothermal Program planning and control document. The Five Year Plans and Multi-Year Plans usually included more detailed rationales and projections than other similar reports. Many of these reports were issued only in draft form. (DJE 2005)

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Molten Salt Oxidation (MSO) is a promising alternative to incineration for the treatment of a variety of organic wastes. Lawrence Livermore National Laboratory (LLNL) has prepared a facility in which an integrated pilot-scale MSO treatment system is being tested and demonstrated. The system consists of a MSO vessel with a dedicated off-gas treatment system, a salt recycle system, feed preparation equipment, and a ceramic final waste forms immobilization system. This integrated system was designed and engineered based on operational experience with an engineering-scale reactor unit and extensive laboratory development on salt recycle and final forms preparation. The MSO/off-gas system has been operational since December 1997. The salt recycle system and the ceramic final forms immobilization became operational in May and August, 1998, respectively. We have tested the MSO facility with various organic feeds, including chlorinated solvents, tributyl phosphate/kerosene, PCB-contaminated waste oils & solvents, booties, plastic pellets, ion exchanged resins, activated carbon, radioactive-spiked organics, and well-characterized low-level liquid mixed wastes. MSO is shown to be a versatile technology for hazardous waste treatment and may be a solution to many waste disposal problems in DOE sites. This report presents the results obtained from operation of the integrated pilot-scale MSO treatment system through …

Previously, the proposers have delivered to ARM a documented algorithm, that is now applied operationally, and which derives water vapor profiles from combined remote sensor measurements of water vapor radiometers, cloud-base ceilometers, and radio acoustic sounding systems (RASS). With the expanded deployment of a Raman lidar at the CART Central Facility, high quality, high vertical-resolution, water vapor profiles will be provided during nighttime clear conditions, and during clear daytime conditions, to somewhat lower altitudes. The object of this effort is to use Kalman Filtering, previously applied to the combination of nighttime Raman lidar and microwave radiometer data, to derive high-quality water vapor profiles, during non-precipitating conditions, from data routinely available at the CART site. Input data to the algorithm would include: Raman lidar data, highly quality-controlled data of integrated moisture from microwave radiometers and GPS, RASS, and radiosondes. The focus of this years activities has been on the intercomparison of data obtained during the Water Vapor Intensive Operating Period'97 at the SGP CART site in central Oklahoma.

This report presents the details of the mission and strategic plan for Lawrence Berkeley Laboratory during the fiscal years of 1995--2000. It presents summaries of current programs and potential changes; critical success factors such as human resources; management practices; budgetary allowances; and technical and administrative initiatives.

The Core Capability and Technical Enhancement (CCTE) Program, a part of the Verification, Validation, and Engineering Assessment Program, was implemented to enhance and augment the technical capabilities of the Idaho National Engineering and Environmental Laboratory (INEEL). The purpose for strengthening the technical capabilities of the INEEL is to provide the technical base to serve effectively as the Environmental Management Laboratory for the Department of Energy's Office of Environmental Management (EM). An analysis of EM's science and technology needs as well as the technology investments currently being made by EM across the complex was used to formulate a portfolio of research activities designed to address EM's needs without overlapping work being done elsewhere. An additional purpose is to enhance and maintain the technical capabilities and research infrastructure at the INEEL. This is a progress report for fiscal year 1998 for the five CCTE research investment areas: (a) transport aspects of selective mass transport agents, (b) chemistry of environmental surfaces, (c) materials dynamics, (d) characterization science, and (e) computational simulation of mechanical and chemical systems. In addition to the five purely technical research areas, this report deals with the science and technology foundations element of the CCTE from the standpoint of program …

This report summarizes the well installation, plugging and abandonment, and redevelopment activities conducted during the federal fiscal year (FY) 1998 at the Y-12 Plant, Oak Ridge, Tennessee. Five new groundwater monitoring wells were installed at the Y-12 Plant under the FY 1998 drilling program. Two of the wells are located in west Bear Creek Valley, one is in the eastern Y-12 Plant area near Lake Reality, and two are located near the Oil Landfarm Waste Management Area, which were installed by Bechtel Jacobs Company LLC (Bechtel Jacobs) as part of a site characterization activity for the Oak Ridge Reservation (ORR) Disposal Cell. Also, two existing wells were upgraded and nine temporary piezometers were installed to characterize hydrogeologic conditions at the Disposal Cell site. In addition, 40 temporary piezometers were installed in the Boneyard/Bumyard area of Bear Creek Valley by Bechtel Jacobs as part of the accelerated remedial actions conducted by the Environmental Restoration Program. Ten monitoring wells at the Y-12 Plant were decommissioned in FY 1998. Two existing monitoring wells were redeveloped during FY 1998 (of these, GW-732 was redeveloped tsvice). All well installation and development (including redevelopment) was conducted following industry-standard methods and approved procedures from the Environmental Surveillance …

The Tanks Focus Area (TFA) serves as the DOE`s Office of Environmental Management`s national technology and solution development program for radioactive waste tank remediation. Its technical scope covers the major functions that comprise a complete tank remediation system: waste retrieval, waste pretreatment, waste immobilization, tank closure, and characterization of both the waste and tank with safety integrated into all the functions. In total, 17 technologies and technical solutions were selected for review. The purpose of each review was to understand the state of development of each technology selected for review and to identify issues to be resolved before the technology or technical solution progressed to the next level of maturity. The reviewers provided detailed technical and programmatic recommendations and comments. The disposition of these recommendations and comments and their impact on the program is documented in this report.

The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels.

This report summarizes waste shipments to the Nevada Test Site Radioactive Waste Management Sites at Area 3 and Area 5 during fiscal year 1998. In addition this report provides a summary evaluation of each shipping campaign by source (waste generator) which identifies observable incidents, if any, associated with the actual waste shipments.

As a way to bootstrap the DISCOM(2) Distance Computing Program the SP2 Pilot Project was launched in March 1998. The Pilot was directed towards creating an environment to allow Sandia users to run their applications on the Accelerated Strategic Computing Initiative's (ASCI) Blue Pacific computation platform, the unclassified IBM SP2 platform at Lawrence Livermore National Laboratory (LLNL). The DISCOM(2) Pilot leverages the ASCI PSE (Problem solving Environment) efforts in networking and services to baseline the performance of the current system. Efforts in the following areas of the pilot are documented: applications, services, networking, visualization, and the system model. It details not only the running of two Sandia codes CTH and COYOTE on the Blue Pacific platform, but also the buildong of the Sandia National Laboratories (SNL) proxy environment of the RS6000 platforms to support the Sandia users.

Two new failure analysis techniques have been developed for backside and front side localization of open and shorted interconnections on ICs. These scanning optical microscopy techniques take advantage of the interactions between IC defects and localized heating using a focused infrared laser ({lambda} = 1,340 nm). Images are produced by monitoring the voltage changes across a constant current supply used to power the IC as the laser beam is scanned across the sample. The methods utilize the Seebeck Effect to localize open interconnections and Thermally-Induced Voltage Alteration (TIVA) to detect shorts. Initial investigations demonstrated the feasibility of TIVA and Seebeck Effect Imaging (SEI). Subsequent improvements have greatly increased the sensitivity of the TIVA/SEI system, reducing the acquisition times by more than 20X and localizing previously unobserved defects. The interaction physics describing the signal generation process and several examples demonstrating the localization of opens and shorts are described. Operational guidelines and limitations are also discussed. The system improvements, non-linear response of IC defects to heating, modeling of laser heating and examples using the improved system for failure analysis are presented.

The 2020 Vision project began in 1996 with two participating teachers and four classes. It has since grown to comprise more than a dozen participating teachers and hundreds of students across the country. Much of this growth took place in FY98, thanks to the accomplishment of several major goals: implementation of a mentor program, enhanced teacher training, a mid-year conference for students, recruitment of distant schools, and the development of an interactive Web site. The first part of this report describes these accomplishments, as well as future directions for 2020 Vision. The second part summarized the scenarios students wrote during the 1997-98 school year. it identifies recurrent themes in the students' scenarios and compares/contrasts them with scenarios written in the first two years of the project.

The U.S. Department of Energy (DOE) continues to face a major radioactive waste tank remediation problem with hundreds of waste tanks containing hundreds of thousands of cubic meters of high-level waste (HLW) and transuranic (TRU) waste across the DOE complex. Approximately 80 tanks are known or assumed to have leaked. Some of the tank contents have reacted to form flammable gases, introducing additional safety risks. These tanks must be maintained in a safe condition and eventually remediated to minimize the risk of waste migration and/or exposure to workers, the public, and the environment. However, programmatic drivers are more ambitious than baseline technologies and budgets will support. Science and technology development investments are required to reduce the technical and programmatic risks associated with the tank remediation baselines. The Tanks Focus Area (TFA) was initiated in 1994 to serve as the DOE`s Office of Environmental Management`s (EM`s) national technology development program for radioactive waste tank remediation. The national program was formed to increase integration and realize greater benefits from DOE`s technology development budget. The TFA is responsible for managing, coordinating, and leveraging technology development to support DOE`s four major tank sites: Hanford Site (Washington), Idaho National Engineering and Environmental Laboratory (INEEL) (Idaho), …

The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels.