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Sample records for facilities deactivating project

  1. 200 Area Deactivation Project Facilities Authorization Envelope Document

    SciTech Connect

    DODD, E.N.

    2000-03-28

    Project facilities as required by HNF-PRO-2701, Authorization Envelope and Authorization Agreement. The Authorization Agreements (AA's) do not identify the specific set of environmental safety and health requirements that are applicable to the facility. Therefore, the facility Authorization Envelopes are defined here to identify the applicable requirements. This document identifies the authorization envelopes for the 200 Area Deactivation.

  2. Work plan for the Isotopes Facilities Deactivation Project at Oak Ridge National Laboratory

    SciTech Connect

    1995-05-01

    The purpose of the Isotopes Facilities Deactivation Project (IFDP) is to place former isotopes production facilities at the Oak Ridge National Laboratory in a safe, stable, and environmentally sound condition; suitable for an extended period of minimum surveillance and maintenance (S&M) and as quickly and economical as possible. Implementation and completion of the deactivation project will further reduce the risks to the environment and to public safety and health. Furthermore, completion of the project will result in significant S&M cost savings in future years. The IFDP work plan defines the project schedule, the cost estimate, and the technical approach for the project. A companion document, the IFDP management plan, has been prepared to document the project objectives, define organizational relationships and responsibilities, and outline the management control systems to be employed in the management of the project. The project has adopted the strategy of deactivating the simple facilities first, to reduce the scope of the project and to gain experience before addressing more difficult facilities. A decision support system is being developed to identify the activities that best promote the project mission and result in the largest cost savings. This work plan will be reviewed and revised annually. Deactivation of IFDP facilities was initiated in FY 1994 and will be completed in FY 1999. The schedule for deactivation of facilities is shown. The total cost of the project is estimated to be $36M. The costs are summarized. Upon completion of deactivation, annual S&M costs of these facilities will be reduced from the current level of $5M per year to less than $1M per year.

  3. Work plan for the Isotopes Facilities Deactivation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1995-08-01

    The purpose of the Isotopes Facilities Deactivation Project (IFDP) is to place former isotopes production facilities at the Oak Ridge National Laboratory in a safe, stable, and environmentally sound condition; suitable for an extended period of minimum surveillance and maintenance (S and M) and as quickly and economical as possible. Implementation and completion of the deactivation project will further reduce the risks to the environment and to public safety and health. Furthermore, completion of the project will result in significant S and M cost savings in future years. The IFDP work plan defines the project schedule, the cost estimate, and the technical approach for the project. A companion document, the EFDP management plan, has been prepared to document the project objectives, define organizational relationships and responsibilities, and outline the management control systems to be employed in the management of the project. The project has adopted the strategy of deactivating the simple facilities first, to reduce the scope of the project and to gain experience before addressing more difficult facilities. A decision support system is being developed to identify the activities that best promote the project mission and result in the largest cost savings. This work plan will be reviewed and revised annually. Deactivation of EFDP Facilities was initiated in FY 1994 and will be completed in FY 2000. The schedule for deactivation of facilities is shown. The total cost of the project is estimated to be $51M. The costs are summarized. Upon completion of deactivation, annual S and M costs of these facilities will be reduced from the current level of $5M per year to less than $1M per year.

  4. Final deactivation project report on the Integrated Process Demonstration Facility, Building 7602 Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1997-09-01

    The purpose of this report is to document the condition of the Integrated Process Demonstration Facility (Building 7602) at Oak Ridge National Laboratory (ORNL) after completion of deactivation activities by the High Ranking Facilities Deactivation Project (HRFDP). This report identifies the activities conducted to place the facility in a safe and environmentally sound condition prior to transfer to the U.S. Department of Energy (DOE) Environmental Restoration EM-40 Program. This report provides a history and description of the facility prior to commencing deactivation activities and documents the condition of the building after completion of all deactivation activities. Turnover items, such as the Post-Deactivation Surveillance and Maintenance (S&M) Plan, remaining hazardous and radioactive materials inventory, radiological controls, Safeguards and Security, and supporting documentation provided in the Office of Nuclear Material and Facility Stabilization Program (EM-60) Turnover package are discussed.

  5. Mission analysis report - deactivation facilities at Hanford

    SciTech Connect

    Lund, D.P.

    1996-09-27

    This document examines the portion of the Hanford Site Cleanup Mission that deals with facility deactivation. How facilities get identified for deactivation, how they enter EM-60 for deactivation, programmatic alternatives to perform facility deactivation, the deactivation process itself, key requirements and objectives associated with the deactivation process, and deactivation planning are discussed.

  6. Health and safety plan for the Isotopes Facilities Deactivation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1996-08-01

    This HASP describes the process for identifying the requirements, written safety documentation, and procedures for protecting personnel involved in the Isotopes Facilities Deactivation Project. Objective of this project is to place 19 former isotope production facilities at ORNL in a safe condition in anticipation of an extended period of minimum surveillance and maintenance.

  7. Life cycle baseline summary for ADS 6504IS Isotopes Facilities Deactivation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1995-11-01

    The purpose of the Isotopes Facility Deactivation Project (IFDP) is to place former isotopes production facilities at the Oak Ridge National Laboratory in a safe, stable, and environmentally sound condition; suitable for an extended period of minimum surveillance and maintenance (S&M) and as quickly and economically as possible. This baseline plan establishes the official target schedule for completing the deactivation work and the associated budget required for deactivation and the necessary S&M. Deactivation of the facilities 3026C, 3026D, 3028, 3029, 3038E, 3038M, and 3038AHF, the Center Circle buildings 3047, 3517, and 7025 will continue though Fiscal Year (FY) 1999. The focus of the project in the early years will be on the smaller buildings that require less deactivation and can bring an early return in reducing S&M costs. This baseline plan covers the period from FY1995 throughout FY2000. Deactivation will continue in various facilities through FY1999. A final year of S&M will conclude the project in FY2000. The estimated total cost of the project during this period is $51M.

  8. Lifecycle baseline summary for ADS 6504IS isotopes facilities Deactivation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1995-08-01

    The scope of this Activity Data Sheet (ADS) is to provide a detailed plan for the Isotopes Facilities Deactivation Project (IFDP) at the Oak Ridge National Laboratory (ORNL). This project places the former isotopes production facilities in a safe, stable, and environmentally sound condition suitable for an extended period of minimum surveillance and maintenance (S&M) until the facilities are included in the Decontamination and Decommissioning (D&D) Program. The facilities included within this deactivation project are Buildings 3026-C, 3026-D, 3028, 3029, 3038-AHF, 3038-E, 3038-M, 3047, 3517, 7025, and the Center Circle Facilities (Buildings 3030, 3031, 3032, 3033, 3033-A, 3034, and 3118). The scope of deactivation identified in this Baseline Report include surveillance and maintenance activities for each facility, engineering, contamination control and structural stabilization of each facility, radioluminescent (RL) light removal in Building 3026, re-roofing Buildings 3030, 3118, and 3031, Hot Cells Cleanup in Buildings 3047 and 3517, Yttrium (Y) Cell and Barricades Cleanup in Building 3038, Glove Boxes & Hoods Removal in Buildings 3038 and 3047, and Inventory Transfer in Building 3517. For a detailed description of activities within this Work Breakdown Structure (WBS) element, see the Level 6 and Level 7 Element Definitions in Section 3.2 of this report.

  9. Work plan for the High Ranking Facilities Deactivation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1996-03-01

    The High Ranking Facilities Deactivation Project (HRFDP), commissioned by the US Department of Energy Nuclear Materials and Facility Stabilization Program, is to place four primary high-risk surplus facilities with 28 associated ancillary facilities at Oak Ridge National Laboratory in a safe, stable, and environmentally sound condition as rapidly and economically as possible. The facilities will be deactivated and left in a condition suitable for an extended period of minimized surveillance and maintenance (S and M) prior to decontaminating and decommissioning (D and D). These four facilities include two reactor facilities containing spent fuel. One of these reactor facilities also contains 55 tons of sodium with approximately 34 tons containing activated sodium-22, 2.5 tons of lithium hydride, approximately 100 tons of potentially contaminated lead, and several other hazardous materials as well as bulk quantities of contaminated scrap metals. The other two facilities to be transferred include a facility with a bank of hot cells containing high levels of transferable contamination and also a facility containing significant quantities of uranyl nitrate and quantities of transferable contamination. This work plan documents the objectives, technical requirements, and detailed work plans--including preliminary schedules, milestones, and conceptual FY 1996 cost estimates--for the Oak Ridge National Laboratory (ORNL). This plan has been developed by the Environmental Restoration (ER) Program of Lockheed Martin Energy Systems (Energy Systems) for the US Department of Energy (DOE) Oak Ridge Operations Office (ORO).

  10. Deactivation, Decontamination and Decommissioning Project Summaries

    SciTech Connect

    Peterson, David Shane; Webber, Frank Laverne

    2001-07-01

    This report is a compilation of summary descriptions of Deactivation, Decontamination and Decommissioning, and Surveillance and Maintenance projects planned for inactive facilities and sites at the INEEL from FY-2002 through FY-2010. Deactivations of contaminated facilities will produce safe and stable facilities requiring minimal surveillance and maintenance pending further decontamination and decommissioning. Decontamination and decommissioning actions remove contaminated facilities, thus eliminating long-term surveillance and maintenance. The projects are prioritized based on risk to DOE-ID, the public, and the environment, and the reduction of DOE-ID mortgage costs and liability at the INEEL.

  11. Final Deactivation Project report on the Alpha Powder Facility, Building 3028, at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1997-04-01

    This report documents the condition of the Alpha Powder Facility (APF), Building 3028, after completion of deactivation activities. Activities conducted to place the facility in a safe and environmentally sound condition for transfer to the U.S. Department of Energy (DOE) Office of Environmental Restoration (EM-40) program are outlined. A history and profile of the facility prior to commencing deactivation activities and a profile of the building after completion of deactivation activities are provided. Turnover items, such as the post-deactivation surveillance and maintenance (S&M) plan, remaining hazardous materials, radiological controls, safeguards and security, quality assurance, facility operations, and supporting documentation provided for in the DOE Nuclear Materials and Facility Stabilization Program (EM-60) turnover package are discussed.

  12. PUREX/UO{sub 3} facilities deactivation lessons learned: History

    SciTech Connect

    Gerber, M.S.

    1997-11-25

    In May 1997, a historic deactivation project at the PUREX (Plutonium URanium EXtraction) facility at the Hanford Site in south-central Washington State concluded its activities (Figure ES-1). The project work was finished at $78 million under its original budget of $222.5 million, and 16 months ahead of schedule. Closely watched throughout the US Department of Energy (DOE) complex and by the US Department of Defense for the value of its lessons learned, the PUREX Deactivation Project has become the national model for the safe transition of contaminated facilities to shut down status.

  13. PUREX/UO{sub 3} facilities deactivation lessons learned history

    SciTech Connect

    Hamrick, D.G.; Gerber, M.S.

    1995-01-01

    The Plutonium-Uranium Extraction (PUREX) Facility operated from 1956-1972, from 1983-1988, and briefly during 1989-1990 to produce for national defense at the Hanford Site in Washington State. The Uranium Trioxide (UO{sub 3}) Facility operated at the Hanford Site from 1952-1972, 1984-1988, and briefly in 1993. Both plants were ordered to permanent shutdown by the U.S. Department of Energy (DOE) in December 1992, thus initiating their deactivation phase. Deactivation is that portion of a facility`s life cycle that occurs between operations and final decontamination and decommissioning (D&D). This document details the history of events, and the lessons learned, from the time of the PUREX Stabilization Campaign in 1989-1990, through the end of the first full fiscal year (FY) of the deactivation project (September 30, 1994).

  14. Final deactivation project report on the High Radiation Level Analytical Facility, Building 3019B at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1997-09-01

    The purpose of this report is to document the condition of the High Radiation Level Analytical Facility (Building 3019B) at Oak Ridge National Laboratory (ORNL) after completion of deactivation activities. This report identifies the activities conducted to place the facility in a safe and environmentally sound condition prior to transfer to the Environmental Restoration EM-40 Program. This document provides a history and description of the facility prior to the commencement of deactivation activities and documents the condition of the building after completion of all deactivation activities. Turnover items, such as the Post-Deactivation Surveillance and Maintenance (S&M) Plan, remaining hazardous materials inventory, radiological controls, safeguards and security, quality assurance, facility operations, and supporting documentation provided in the Nuclear Material and Facility Stabilization (EM-60) Turnover package are discussed. Building 3019B will require access to perform required S&M activities to maintain the building safety envelope. Building 3019B was stabilized during deactivation so that when transferred to the EM-40 Program, only a minimal S&M effort would be required to maintain the building safety envelope. Other than the minimal S&M activities the building will be unoccupied and the exterior doors locked to prevent unauthorized access. The building will be entered only to perform the required S&M until decommissioning activities begin.

  15. PUREX/UO3 Facilities deactivation lessons learned history

    SciTech Connect

    Gerber, M.S.

    1996-09-19

    accompanied by and were an integral part of sweeping ``culture changes,`` the story of the lessons learned during the PUREX Deactivation Project are worth recounting. Foremost among the lessons is recognizing the benefits of ``right to left`` project planning. A deactivation project must start by identifying its end points, then make every task, budget, and organizational decision based on reaching those end points. Along with this key lesson is the knowledge that project planning and scheduling should be tied directly to costing, and the project status should be checked often (more often than needed to meet mandated reporting requirements) to reflect real-time work. People working on a successful project should never be guessing about its schedule or living with a paper schedule that does not represent the actual state of work. Other salient lessons were learned in the PUREX/UO3 Deactivation Project that support these guiding principles. They include recognizing the value of independent review, teamwork, and reengineering concepts; the need and value of cooperation between the DOE, its contractors, regulators, and stakeholders; and the essential nature of early and ongoing communication. Managing a successful project also requires being willing to take a fresh look at safety requirements and to apply them in a streamlined and sensible manner to deactivating facilities; draw on the enormous value of resident knowledge acquired by people over years and sometimes decades of working in old plants; and recognize the value of bringing in outside expertise for certain specialized tasks.This approach makes possible discovering the savings that can come when many creative options are pursued persistently and the wisdom of leaving some decisions to the future. The essential job of a deactivation project is to place a facility in a safe, stable, low-maintenance mode, for an interim period. Specific end points are identified to recognize and document this state. Keeping the limited

  16. 1997 project of the year, PUREX deactivation project

    SciTech Connect

    Bailey, R.W.

    1998-02-13

    At the end of 1992, the PUREX and UO{sub 3} plants were deemed no longer necessary for the defense needs of the United States. Although no longer necessary, they were very costly to maintain in their post-operation state. The DOE embarked on a deactivation strategy for these plants to reduce the costs of providing continuous surveillance of the facilities and their hazards. Deactivation of the PUREX and UO{sub 3} plants was estimated to take 5 years and cost $222.5 million and result in an annual surveillance and maintenance cost of $2 million. Deactivation of the PUREX/UO{sub 3} plants officially began on October 1, 1993. The deactivation was 15 months ahead of the original schedule and $75 million under the original cost estimate. The annual cost of surveillance and maintenance of the plants was reduced to less than $1 million.

  17. Accelerating deactivation

    SciTech Connect

    FISHBACK, K.M.

    1999-02-01

    In recent years, the focus of the U.S. Department of Energy (DOE) complex has shifted from defense production to facility stabilization, decommissioning, and environmental restoration. This shift from production to cleanup requires a parallel shift from operations-focused management to project-focused management for an efficient facility deactivation. In the operation-focused management organization, activities are planned and executed based on production goals and are typically repetitive and cyclic. In the project-focused management environment, activities are based on a defined scope/end objective, start date, and completion date. Since the workforce used to perform production operations is also usually relied onto perform facility deactivation, it is important to shift from an operations management approach to a project management approach. It is best if the transition is accomplished quickly so the project can move forward and workers don't spend a lot of energy anticipating change. Therefore, it is essential that managers, planners, and other workers understand the key elements associated with planning a deactivation project. This paper describes a planning approach that has been used successfully to plan deactivation projects consistent with the requirements provided in DOE Order 430.1A Life Cycle Asset Management and the companion Deactivation Implementation Guide, G430. 1A-3, while exceeding schedule expectations and reducing costs. Although the planning of a deactivation project closely mirrors the classic project planning for construction projects, there are unique variations associated with facility deactivation. The key elements of planning a deactivation project are discussed relative to scope, schedule, and cost. Management tools such as project metrics and histograms are discussed as desired outputs from the planning process. In addition, lessons learned from planning deactivation projects across the DOE complex are discussed relative to making the

  18. Integrated project management plan for the Plutonium Finishing Plant stabilization and deactivation project

    SciTech Connect

    SINCLAIR, J.C.

    1999-05-03

    This document sets forth the plans, organization, and control systems for managing the PFP Stabilization and Deactivation Project, and includes the top level cost and schedule baselines. The project includes the stabilization of Pu-bearing materials, storage, packaging, and transport of these and other nuclear materials, surveillance and maintenance of facilities and systems relied upon for storage of the materials, and transition of the facilities in the PFP Complex.

  19. Chemicals and excess materials disposition during facility deactivation as a means of pollution prevention

    SciTech Connect

    Godfrey, S.D.

    1998-05-28

    This paper presents several innovative and common sense approaches to pollution prevention that have been employed during facility deactivation at the Hanford Site in South Central Washington. It also presents several pollution prevention principles applicable to other projects. Innovative pollution prevention ideas employed at the Hanford site during facility deactivation included: (1) Recycling more than 185,000 gallons of radioactively contaminated nitric acid by sending it to an operating nuclear fuels reprocessing facility in England; (2) Recycling millions of pounds of chemicals and excess materials to other industries for reuse; (3) Evaporating flush water at a low rate and discharging it into the facility exhaust air stream to avoid discharging thousands of gallons of liquid to the soil column; and (4) Decontaminating and disposing of thousands of gallons of radioactively contaminated organic solvent waste to a RCRA licensed, power-producing, commercial incinerator. Common sense pollution prevention ideas that were employed include recycling office furniture, recycling paper from office files, and redeploying tools and miscellaneous process equipment. Additional pollution prevention occurred as the facility liquid and gaseous discharge streams were deactivated. From the facilities deactivation experiences at Hanford and the ensuing efforts to disposition excess chemicals and materials, several key pollution prevention principles should be considered at other projects and facilities, especially during the operational periods of the facility`s mission. These principles include: Institute pollution prevention as a fundamental requirement early in the planning stage of a project or during the operational phase of a facility`s mission; Promote recognition and implementation of pollution prevention initiatives; Instill pollution prevention as a value in all participants in the project or facility work scope; Minimize the amount of chemical products and materials

  20. 49 CFR 192.727 - Abandonment or deactivation of facilities.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 49 Transportation 3 2013-10-01 2013-10-01 false Abandonment or deactivation of facilities. 192.727 Section 192.727 Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY TRANSPORTATION OF NATURAL AND OTHER GAS...

  1. FACILITY DEACTIVATION AND DECOMMISSIONING AT THE SAVANNAH RIVER SITE

    SciTech Connect

    Gilmour, J; William Austin, W; Cathy Sizemore, C

    2007-01-31

    In February 2002, the U.S. Department of Energy initiated actions to expedite Cleanup, focus on significant and early risk reduction, and reduce costs at the Savannah River Site (SRS). In response SRS started on a project focused on completing the decommissioning of inactive facilities in T, D, and M Areas, areas that on the perimeter of the Site, by the end of 2006. In June 2003, the Department of Energy Savannah River Operations Office (DOE-SR), the South Carolina Department of Health and Environmental Control (SCDHEC), and the Environmental Protection Agency, Region 4 (EPA-4) endorsed a Memorandum of Agreement (MOA) concerning cleanup at the Savannah River Site (SRS). The vision of the Agreement is that SRS will reduce its operations footprint to establish a buffer zone at the perimeter if the Site, while the central core area of the Site will be reserved for continuing or future long-term operations. DOE-SR, EPA-4, and SCDHEC agreed that establishing this buffer zone and appropriately sequencing environmental restoration and decommissioning activities can lead to greater efficiency and accelerate completion of entire site areas. This vision is embodied in the concept of Area Completion--which integrated operations, deactivation and decommissioning (D&D), and soils and groundwater cleanup into a time-phased approach to completing all the work necessary to address the Cold War legacy. D&D addresses the ''footprint'' of the building or structure, while the soils and groundwater project addresses any environmental remediation that may be required in the underlying and surrounding soils and groundwater. Since then, {approx}250 facilities have been decommissioned at the SRS, ranging from guard stations to nuclear fuel production facilities.

  2. Audit of the deactivation, decontamination, and disposal of surplus facilities at the Savannah River Site

    SciTech Connect

    1997-10-23

    Westinghouse Savannah River Company (Westinghouse) is responsible for managing the Department of Energy`s (Department) surplus facilities at the Savannah River Site (Site). In Fiscal Year (FY) 1996, the Site had 162 surplus facilities and anticipated that 118 more would become surplus within the next 5 years. The objective of this audit was to determine whether the Savannah River Operations Office (Operations Office) and Westinghouse had economically and promptly deactivated, decontaminated, and disposed of surplus facilities at the Site. Departmental regulations require that surplus facilities be deactivated, decontaminated, and disposed of economically and promptly. However, Westinghouse only disposed of one facility and did not completely deactivate or decontaminate any of the 162 facilities identified as surplus at the Site in FY 1996. This occurred because the Operations Office did not compile a Site-wide list, establish priorities, or provide sufficient funding for the deactivation, decontamination, and disposal of surplus facilities. As a result, the Department incurred unnecessary costs for the surveillance and maintenance of surplus facilities. For example, the Department could have avoided annual costs of about $1.3 million in surveillance and maintenance costs by spending $1.2 million to perform a deactivation project on the P-Reactor process-water storage tanks. The Operations Office could have funded the project out of its unobligated FY 1996 operating funds. However, it returned the unobligated funds to the Department`s Headquarters at the end of the fiscal year. The Operations Office concurred with the finding and recommendations and initiated corrective action.

  3. PUREX/UO{sub 3} deactivation project management plan

    SciTech Connect

    Washenfelder, D.J.

    1993-12-01

    From 1955 through 1990, the Plutonium-Uranium Extraction Plant (PUREX) provided the United States Department of Energy Hanford Site with nuclear fuel reprocessing capability. It operated in sequence with the Uranium Trioxide (UO{sub 3}) Plant, which converted the PUREX liquid uranium nitrate product to solid UO{sub 3} powder. Final UO{sub 3} Plant operation ended in 1993. In December 1992, planning was initiated for the deactivation of PUREX and UO{sub 3} Plant. The objective of deactivation planning was to identify the activities needed to establish a passively safe, environmentally secure configuration at both plants, and ensure that the configuration could be retained during the post-deactivation period. The PUREX/UO{sub 3} Deactivation Project management plan represents completion of the planning efforts. It presents the deactivation approach to be used for the two plants, and the supporting technical, cost, and schedule baselines. Deactivation activities concentrate on removal, reduction, and stabilization of the radioactive and chemical materials remaining at the plants, and the shutdown of the utilities and effluents. When deactivation is completed, the two plants will be left unoccupied and locked, pending eventual decontamination and decommissioning. Deactivation is expected to cost $233.8 million, require 5 years to complete, and yield $36 million in annual surveillance and maintenance cost savings.

  4. Commercial experience with facility deactivation to safe storage

    SciTech Connect

    Sype, T.T.; Fischer, S.R.; Lee, J.H. Jr.; Sanchez, L.C.; Ottinger, C.A.; Pirtle, G.J.

    1995-09-01

    The Department of Energy (DOE) has shutdown many production reactors; the Department has begun a major effort to also shutdown a wide variety of other nuclear facilities. Because so many facilities are being closed, it is necessary to place many of them into a safe- storage status, i.e., deactivation, before conducting decommissioning- for perhaps as long as 20 years. The challenge is to achieve this safe-storage condition in a cost-effective manner while remaining in compliance with applicable regulations. The DOE Office of Environmental Management, Office of Transition and Management, commissioned a lessons-learned study of commercial experience with safe storage and decommissioning. Although the majority of the commercial experience has been with reactors, many of the lessons learned presented in this document can provide insight into transitioning challenges that Will be faced by the DOE weapons complex.

  5. PROJECTIZING AN OPERATING NUCLEAR FACILITY

    SciTech Connect

    Adams, N

    2007-07-08

    This paper will discuss the evolution of an operations-based organization to a project-based organization to facilitate successful deactivation of a major nuclear facility. It will describe the plan used for scope definition, staff reorganization, method estimation, baseline schedule development, project management training, and results of this transformation. It is a story of leadership and teamwork, pride and success. Workers at the Savannah River Site's (SRS) F Canyon Complex (FCC) started with a challenge--take all the hazardous byproducts from nearly 50 years of operations in a major, first-of-its-kind nuclear complex and safely get rid of them, leaving the facility cold, dark, dry and ready for whatever end state is ultimately determined by the United States Department of Energy (DOE). And do it in four years, with a constantly changing workforce and steadily declining funding. The goal was to reduce the overall operating staff by 93% and budget by 94%. The facilities, F Canyon and its adjoined sister, FB Line, are located at SRS, a 310-square-mile nuclear reservation near Aiken, S.C., owned by DOE and managed by Washington Group International subsidiary Washington Savannah River Company (WSRC). These facilities were supported by more than 50 surrounding buildings, whose purpose was to provide support services during operations. The radiological, chemical and industrial hazards inventory in the old buildings was significant. The historical mission at F Canyon was to extract plutonium-239 and uranium-238 from irradiated spent nuclear fuel through chemical processing. FB Line's mission included conversion of plutonium solutions into metal, characterization, stabilization and packaging, and storage of both metal and oxide forms. The plutonium metal was sent to another DOE site for use in weapons. Deactivation in F Canyon began when chemical separations activities were completed in 2002, and a cross-functional project team concept was implemented to successfully

  6. PLUTONIUM FINISHING PLANT (PFP) 241-Z LIQUID WASTE TREATMENT FACILITY DEACTIVATION AND DEMOLITION

    SciTech Connect

    JOHNSTON GA

    2008-01-15

    Fluor Hanford, Inc. (FH) is proud to submit the Plutonium Finishing Plant (PFP) 241-Z liquid Waste Treatment Facility Deactivation and Demolition (D&D) Project for consideration by the Project Management Institute as Project of the Year for 2008. The decommissioning of the 241-Z Facility presented numerous challenges, many of which were unique with in the Department of Energy (DOE) Complex. The majority of the project budget and schedule was allocated for cleaning out five below-grade tank vaults. These highly contaminated, confined spaces also presented significant industrial safety hazards that presented some of the most hazardous work environments on the Hanford Site. The 241-Z D&D Project encompassed diverse tasks: cleaning out and stabilizing five below-grade tank vaults (also called cells), manually size-reducing and removing over three tons of process piping from the vaults, permanently isolating service utilities, removing a large contaminated chemical supply tank, stabilizing and removing plutonium-contaminated ventilation ducts, demolishing three structures to grade, and installing an environmental barrier on the demolition site . All of this work was performed safely, on schedule, and under budget. During the deactivation phase of the project between November 2005 and February 2007, workers entered the highly contaminated confined-space tank vaults 428 times. Each entry (or 'dive') involved an average of three workers, thus equaling approximately 1,300 individual confined -space entries. Over the course of the entire deactivation and demolition period, there were no recordable injuries and only one minor reportable skin contamination. The 241-Z D&D Project was decommissioned under the provisions of the 'Hanford Federal Facility Agreement and Consent Order' (the Tri-Party Agreement or TPA), the 'Resource Conservation and Recovery Act of 1976' (RCRA), and the 'Comprehensive Environmental Response, Compensation, and Liability Act of 1980' (CERCLA). The

  7. Fast Flux Test Facility project plan. Revision 2

    SciTech Connect

    Hulvey, R.K.

    1995-11-01

    The Fast Flux Test Facility (FFTF) Transition Project Plan, Revision 2, provides changes to the major elements and project baseline for the deactivation activities necessary to transition the FFTF to a radiologically and industrially safe shutdown condition.

  8. Integrated Project Management Planning for the Deactivation of the Savannah River Site F-Canyon Complex

    SciTech Connect

    Clark, T.G.

    2000-12-01

    This paper explains the planning process that is being utilized by the Westinghouse Savannah River Company to take the F-Canyon Complex facilities from operations to a deactivated condition awaiting final decommissioning.

  9. 340 waste handling complex: Deactivation project management plan

    SciTech Connect

    Stordeur, R.T.

    1998-06-25

    This document provides an overview of the strategy for deactivating the 340 Waste Handling Complex within Hanford`s 300 Area. The plan covers the period from the pending September 30, 1998 cessation of voluntary radioactive liquid waste (RLW) transfers to the 340 Complex, until such time that those portions of the 340 Complex that remain active beyond September 30, 1998, specifically, the Retention Process Sewer (RPS), can also be shut down and deactivated. Specific activities are detailed and divided into two phases. Phase 1 ends in 2001 after the core RLW systems have been deactivated. Phase 2 covers the subsequent interim surveillance of deactivated and stand-by components during the period of continued RPS operation, through the final transfer of the entire 340 Complex to the Environmental Restoration Contractor. One of several possible scenarios was postulated and developed as a budget and schedule planning case.

  10. HE Machining Complex and Support Buildings Deactivation and Decommissioning Project at the Pantex Plant

    SciTech Connect

    Lyles, C.; Conner, M.

    2007-07-01

    This paper describes the issues related to the deactivation and decommissioning of a very unique building at the Department of Energy's Pantex Plant located in Amarillo, TX. Building 12-24 was unique in the fact that it had a number of obstacles that have not been previously addressed in the deactivation and decommissioning of a single structure such as asbestos, beryllium, possible radionuclide contamination, lead paint, heavily reinforced concrete walls, and high explosive (HE) contamination inside and out. To date, the building has been razed and the majority of all equipment has been disposed of. Remaining work includes concrete and soil debris removal, earthen barricade removal, and site leveling. Pantex Site Summary: Pantex Plant is America's only nuclear weapons assembly and disassembly facility. Located on the High Plains of the Texas Panhandle, 17 miles northeast of Amarillo, Pantex is centered on a 16,000-acre site just north of U. S. Highway 60 in Carson County. The Pantex Plant industrial operations are conducted for the DOE by a management and operating contractor (BWXT Pantex), and Sandia National Laboratory. DOE owns approximately 9,100 acres at the Pantex Plant. Just over 2,000 acres of the DOE-owned property are used for industrial operations at Pantex Plant excluding the burning ground, firing sites and other outlying areas. The burning ground and firing sites occupy approximately 489 acres. Remaining DOE-owned land serves DOE safety and security purposes. DOE also owns Pantex Lake, a detached piece of property approximately 4 km (2.5 mi) northeast of the main Plant site that comprises 1,077 acres; the playa lake-bed itself occupying approximately 800 acres. Currently no government industrial operations are conducted at the Pantex Lake property. Seventy-six kilometers (47 mi) of roads exist within the Pantex Plant boundaries. Project Summary: Facilities are deactivated and decommissioned (D and D) when there is no longer a mission for them or they

  11. Oak Ridge National Laboratory Facilities Revitalization Project - Project Management Plan

    SciTech Connect

    Myrick, T.E.

    2000-06-06

    The Facilities Revitalization Project (FRP) has been established at Oak Ridge National Laboratory (ORNL) to provide new and/or refurbished research and support facilities for the Laboratory's science mission. The FRP vision is to provide ORNL staff with world-class facilities, consolidated at the X-10 site, with the first phase of construction to be completed within five years. The project will utilize a combination of U.S. Department of Energy (DOE), State of Tennessee, and private-sector funds to accomplish the new construction, with the facilities requirements to be focused on support of the ORNL Institutional Plan. This FRP Project Management Plan has been developed to provide the framework under which the project will be conducted. It is intended that the FRP will be managed as a programmatic office, with primary resources for execution of the project to be obtained from the responsible organizations within ORNL (Engineering, Procurement, Strategic Planning, etc.). The FRP Project Management Plan includes a definition of the project scope, the organizational responsibilities, and project approach, including detailed Work Breakdown Structure (WBS), followed by more detailed discussions of each of the main WBS elements: Project Planning Basis, Facility Deactivation and Consolidation, and New Facilities Development. Finally, a general discussion of the overall project schedule and cost tracking approach is provided.

  12. REVIEW OF INDUSTRIES AND GOVERNMENT AGENCIES FOR TECHNOLOGIES APPLICABLE TO DEACTIVATION AND DECOMMISSIONING OF NUCLEAR WEAPONS FACILITIES

    SciTech Connect

    Reilkoff, T. E.; Hetland, M. D.; O'Leary, E. M.

    2002-02-25

    The Deactivation and Decommissioning Focus Area's (DDFA's) mission is to develop, demonstrate, and deploy improved deactivation and decommissioning (D&D) technologies. This mission requires that emphasis be continually placed on identifying technologies currently employed or under development in other nuclear as well as nonnuclear industries and government agencies. In support of DDFA efforts to clean up the U.S. Department of Energy's (DOE's) radiologically contaminated surplus facilities using technologies that improve worker safety, reduce costs, and accelerate cleanup schedules, a study was conducted to identify innovative technologies developed for use in nonnuclear arenas that are appropriate for D&D applications.

  13. The Challenges of Preserving Historic Resources During the Deactivation and Decommissioning of Highly Contaminated Historically Significant Plutonium Process Facilities

    SciTech Connect

    Hopkins, A.; Minette, M.; Sorenson, D.; Heineman, R.; Gerber, M.; Charboneau, S.; Bond, F.

    2006-07-01

    The Manhattan Project was initiated to develop nuclear weapons for use in World War II. The Hanford Engineer Works (HEW) was established in eastern Washington State as a production complex for the Manhattan Project. A major product of the HEW was plutonium. The buildings and process equipment used in the early phases of nuclear weapons development are historically significant because of the new and unique work that was performed. When environmental cleanup became Hanford's central mission in 1991, the Department of Energy (DOE) prepared for the deactivation and decommissioning of many of the old process facilities. In many cases, the process facilities were so contaminated, they faced demolition. The National Historic Preservation Act (NHPA) requires federal agencies to evaluate the historic significance of properties under their jurisdiction for eligibility for inclusion in the National Register of Historic Places before altering or demolishing them so that mitigation through documentation of the properties can occur. Specifically, federal agencies are required to evaluate their proposed actions against the effect the actions may have on districts, sites, buildings or structures that are included or eligible for inclusion in the National Register. In an agreement between the DOE's Richland Operations Office (RL), the Washington State Historic Preservation Office (SHPO) and the Advisory Council on Historic Preservation (ACHP), the agencies concurred that the Hanford Site Historic District is eligible for listing on the National Register of Historic Places and that a Site-wide Treatment Plan would streamline compliance with the NHPA while allowing RL to manage the cleanup of the Hanford Site. Currently, many of the old processing buildings at the Plutonium Finishing Plant (PFP) are undergoing deactivation and decommissioning. RL and Fluor Hanford project managers at the PFP are committed to preserving historical artifacts of the plutonium production process. They

  14. Decontamination and deactivation of the power burst facility at the Idaho National Laboratory.

    PubMed

    Greene, Christy Jo

    2007-05-01

    Successful decontamination and deactivation of the Power Burst Facility located at the Idaho National Laboratory was accomplished through the use of extensive planning, job sequencing, engineering controls, continuous radiological support, and the use of a dedicated group of experienced workers. Activities included the removal and disposal of irradiated fuel, miscellaneous reactor components and debris stored in the canal, removal and disposition of a 15.6 curie Pu:Be start-up source, removal of an irradiated in-pile tube, and the removal of approximately 220,000 pounds of lead that was used as shielding primarily in Cubicle 13. The canal and reactor vessel were drained and water was transferred to an evaporation tank adjacent to the facility. The canal was decontaminated using underwater divers, and epoxy was affixed to the interior surfaces of the canal to contain loose contamination. The support structures and concrete or steel frame walls that form the confinement were left in place. The reactor core was left in place and a carbon steel shielding plate was placed over the reactor core to reduce radiation levels. All low-level waste and mixed low level waste generated as a result of the work activities was characterized and disposed. PMID:17440324

  15. THE DEACTIVATION DECONTAMINATION & DECOMMISSIONING OF THE PLUTONIUM FINISHING PLANT (PFP) A FORMER PLUTONIUM PROCESSING FACILITY AT DOE HANFORD SITE

    SciTech Connect

    CHARBONEAU, S.L.

    2006-02-01

    The Plutonium Finishing Plant (PFP) was constructed as part of the Manhattan Project during World War II. The Manhattan Project was developed to usher in the use of nuclear weapons to end the war. The primary mission of the PFP was to provide plutonium used as special nuclear material (SNM) for fabrication of nuclear devices for the war effort. Subsequent to the end of World War II, the PFP's mission expanded to support the Cold War effort through plutonium production during the nuclear arms race and later the processing of fuel grade mixed plutonium-uranium oxide to support DOE's breeder reactor program. In October 1990, at the close of the production mission for PFP, a shutdown order was prepared by the Department of Energy (DOE) in Washington, DC and issued to the Richland DOE field office. Subsequent to the shutdown order, a team from the Defense Nuclear Facilities Safety Board (DNFSB) analyzed the hazards at PFP associated with the continued storage of certain forms of plutonium solutions and solids. The assessment identified many discrete actions that were required to stabilize the different plutonium forms into stable form and repackage the material in high integrity containers. These actions were technically complicated and completed as part of the PFP nuclear material stabilization project between 1995 and early 2005. The completion of the stabilization project was a necessary first step in deactivating PFP. During stabilization, DOE entered into negotiations with the U.S. Environmental Protection Agency (EPA) and the State of Washington and established milestones for the Deactivation and Decommissioning (D&D) of the PFP. The DOE and its contractor, Fluor Hanford (Fluor), have made great progress in deactivating, decontaminating and decommissioning the PFP at the Hanford Site as detailed in this paper. Background information covering the PFP D&D effort includes descriptions of negotiations with the State of Washington concerning consent-order milestones

  16. Idaho Cleanup Project CPP-603A basin deactivation waste management 2007

    SciTech Connect

    Croson, D.V.; Davis, R.H.; Cooper, W.B.

    2007-07-01

    The CPP-603A basin facility is located at the Idaho Nuclear Technology and Engineering Center (INTEC) at the U.S. Department of Energy's (DOE) Idaho National Laboratory (INL). CPP-603A operations are part of the Idaho Cleanup Project (ICP) that is managed by CH2M-WG Idaho, LLC (CWI). Once the inventoried fuel was removed from the basins, they were no longer needed for fuel storage. However, they were still filled with water to provide shielding from high activity debris and contamination, and had to either be maintained so the basins did not present a threat to public or worker health and safety, or be isolated from the environment. The CPP-603A basins contained an estimated 50,000 kg (110,200 lbs) of sludge. The sludge was composed of desert sand, dust, precipitated corrosion products, and metal particles from past cutting operations. The sediment also contained hazardous constituents and radioactive contamination, including cadmium, lead, and U-235. An Engineering Evaluation/Cost Analysis (EE/CA), conducted pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), evaluated the risks associated with deactivation of the basins and the alternatives for addressing those risks. The recommended action identified in the Action Memorandum was to perform interim stabilization of the basins. The sludge in the basins was removed and treated in accordance with the Hazardous Waste Management Act/Resource Conservation and Recovery Act (HWMA/RCRA) and disposed at the INL Radioactive Waste Management Complex (RWMC). A Non-Time Critical Removal Action (NTCRA) was conducted under CERCLA to reduce or eliminate other hazards associated with maintaining the facility. The CERCLA NTCRA included removing a small high-activity debris object (SHADO 1); consolidating and mapping the location of debris objects containing Co-60; removing, treating, and disposing of the basin water; and filling the basins with grout/controlled low strength material (CLSM

  17. Fast flux test facility, transition project plan

    SciTech Connect

    Guttenberg, S.

    1994-11-15

    The FFTF Transition Project Plan, Revision 1, provides changes and project baseline for the deactivation activities necessary to transition the FFTF to a radiologically and industrially safe shutdown condition.

  18. PCB regulations and their application to deactivation and decommissioning activities: Technical assistance project

    SciTech Connect

    1996-04-01

    DOE`s economic development plans involve efforts to deactivate and decommission or refurbish site buildings and operational facilities for other uses. Site personnel must decide on disposition of stored materials, which include increasing numbers of excess and/or unwanted oil-filled equipment (e.g., transformers, hydraulic systems, heat transfer systems) and oil-containing `orphaned` drums. Because oil and these items can also contain polychlorinated biphenyls, it is essential that site personnel become aware of the regulations applicable to PCBs (adherence will minimize DOE hazardous material management liabilities). A recent incident at a DOE facility provides a case in point with important lessons to be learned for all sites within the DOE complex.

  19. Successful integration of pollution prevention strategies during deactivation and decommissioning of chemistry R{ampersand}D facilities

    SciTech Connect

    Burgin, C.D.; Waterman, M.A.

    1997-08-29

    The Chemistry & Materials Sciences (C&MS) Directorate is in the third year of a four-year space consolidation plan. In 1994, approximately half of the total directorate square footage was comprised of 40-year old wet chemistry research buildings that had exceeded their useful life and were viewed a legacy facilities to the program. This mix of old vs. new laboratory space was not properly aligned nor suited for future needs of C&MS, from both the cultural or economic position, thus change was needed. C&MS instituted an aggressive, strategic, business-driven space consolidation initiative, called SAT (Space Action Team), to optimize space utilization, reduce annual costs, meet strategic program needs, and consolidate activities by functional area. The plan called for a 4-year process beginning in FY95 to realign the directorate`s facility portfolio through relocations, consolidations, transfer of facility ownership, demolition of trailers and new construction with a 20% sq/ft reduction as an end goal. As with all business driven initiatives, existing operating costs, implementation costs, cost avoidance and future operating costs were key metrics to measure against the strategic goal. Where P2 was not an essential element in the strategic planning process, it played a key role in the continuing success of the process. SAT is in year three of the four year plan (approximate $5 million investment), which has made a major contribution to the success of C&MS by achieving the directorate`s goals of improving the utilization of space by 30%, increasing quality of the facilities, and reducing annual operating costs. To date, SAT has achieved an on-going organizational facility charge saving of $2 million /year, minimized Program downtime, transferred 120,000 sq ft to new owners, relocated 86 labs, vacated 9 buildings, deactivate, decommissioned and decontaminated four 40 plus year old R&D facilities, and demolished 9 trailers with no incidents or injuries. Our process cost

  20. Canastota Renewable Energy Facility Project

    SciTech Connect

    Blake, Jillian; Hunt, Allen

    2013-12-13

    The project was implemented at the Madison County Landfill located in the Town of Lincoln, Madison County, New York. Madison County has owned and operated the solid waste and recycling facilities at the Buyea Road site since 1974. At the onset of the project, the County owned and operated facilities there to include three separate landfills, a residential solid waste disposal and recycled material drop-off facility, a recycling facility and associated administrative, support and environmental control facilities. This putrescible waste undergoes anaerobic decomposition within the waste mass and generates landfill gas, which is approximately 50% methane. In order to recover this gas, the landfill was equipped with gas collection systems on both the east and west sides of Buyea Road which bring the gas to a central point for destruction. In order to derive a beneficial use from the collected landfill gases, the County decided to issue a Request for Proposals (RFP) for the future use of the generated gas.

  1. Space infrared telescope facility project

    NASA Technical Reports Server (NTRS)

    Cruikshank, Dale P.

    1988-01-01

    The functions undertaken during this reporting period were: to inform the planetary science community of the progress and status of the Space Infrared Telescope Facility (SIRTF) Project; to solicit input from the planetary science community on needs and requirements of planetary science in the use of SIRTF at such time that it becomes an operational facility; and a white paper was prepared on the use of the SIRTF for solar system studies.

  2. The National Ignition Facility Project

    SciTech Connect

    Paisner, J.A.; Campbell, E.M.; Hogan, W.J.

    1994-06-16

    The mission of the National Ignition Facility is to achieve ignition and gain in ICF targets in the laboratory. The facility will be used for defense applications such as weapons physics and weapons effect testing, and for civilian applications such as fusion energy development and fundamental studies of matter at high temperatures and densities. This paper reviews the design, schedule and costs associated with the construction project.

  3. Fast Flux Test Facility transition project resource loaded schedule. Revision 1

    SciTech Connect

    Hulvey, R.K.

    1994-10-31

    Revision 1 of the Fast Flux Test Facility (FFTF) Transition Project Resource Loaded Schedule (RLS) provides detail to manage the major elements, project baseline and cost estimate for the FFF Transition Project within the Advanced Reactors Transition Program, comprised of Activity Data Sheets (ADS) 6640, 6641, and 6642. The scope includes all work in the Budget and Reporting categories of Program Integration (PI), Surveillance and Maintenance (S and M), and Deactivation/Compliance (D/C). The transition activities are necessary to bring the FFTF and related facilities to a safe deactivation state, while maintaining worker health and safety. The scope of ADS 6640 and 6642 is the FFTF Transition Project while the scope of ADS 6641 is the Hanford Site Nuclear Energy Legacies.

  4. Heritage Park Facilities PV Project

    SciTech Connect

    Hobaica, Mark

    2013-09-26

    Project Objective: To procure a photovoltaic array (PV) system which will generate approximately 256kW of power to be used for the operations of the Aquatic Complex and the adjacent Senior Facility at the Heritage Park. This project complies with the EERE’s work and objectives by promoting the development and deployment of an energy system that will provide current and future generations with clean, efficient, affordable, and reliable energy.

  5. Mississippi Test Facility research projects

    NASA Technical Reports Server (NTRS)

    Whitehurst, C. A.

    1974-01-01

    Research capabilities of Louisiana State University are reported for sustaining a program which complements the Mississippi Test Facility. Projects reported during this period are discussed and include the development of a spectral analyzer, and investigations of plant physiology. Papers published during this period are also listed.

  6. HEU Measurements of Holdup and Recovered Residue in the Deactivation and Decommissioning Activities of the 321-M Reactor Fuel Fabrication Facility at the Savannah River Site

    SciTech Connect

    DEWBERRY, RAYMOND; SALAYMEH, SALEEM R.; CASELLA, VITO R.; MOORE, FRANK S.

    2005-03-11

    This paper contains a summary of the holdup and material control and accountability (MC&A) assays conducted for the determination of highly enriched uranium (HEU) in the deactivation and decommissioning (D&D) of Building 321-M at the Savannah River Site (SRS). The 321-M facility was the Reactor Fuel Fabrication Facility at SRS and was used to fabricate HEU fuel assemblies, lithium-aluminum target tubes, neptunium assemblies, and miscellaneous components for the SRS production reactors. The facility operated for more than 35 years. During this time thousands of uranium-aluminum-alloy (U-Al) production reactor fuel tubes were produced. After the facility ceased operations in 1995, all of the easily accessible U-Al was removed from the building, and only residual amounts remained. The bulk of this residue was located in the equipment that generated and handled small U-Al particles and in the exhaust systems for this equipment (e.g., Chip compactor, casting furnaces, log saw, lathes A & B, cyclone separator, Freon{trademark} cart, riser crusher, ...etc). The D&D project is likely to represent an important example for D&D activities across SRS and across the Department of Energy weapons complex. The Savannah River National Laboratory was tasked to conduct holdup assays to quantify the amount of HEU on all components removed from the facility prior to placing in solid waste containers. The U-235 holdup in any single component of process equipment must not exceed 50 g in order to meet the container limit. This limit was imposed to meet criticality requirements of the low level solid waste storage vaults. Thus the holdup measurements were used as guidance to determine if further decontamination of equipment was needed to ensure that the quantity of U-235 did not exceed the 50 g limit and to ensure that the waste met the Waste Acceptance Criteria (WAC) of the solid waste storage vaults. Since HEU is an accountable nuclear material, the holdup assays and assays of recovered

  7. Gamma-4 electrophysical facility project

    NASA Astrophysics Data System (ADS)

    Zavyalov, N. V.; Gordeev, V. S.; Punin, V. T.; Grishin, A. V.; Nazarenko, S. T.; Pavlov, V. S.; Demanov, V. A.; Shikhanova, T. F.; Kalashnikov, D. A.; Kozachek, A. V.; Glushkov, S. L.; Strabykin, K. V.; Puchagin, S. Yu.; Mansurov, D. O.; Mironychev, B. P.; Maiorov, R. A.; Maiornikova, V. L.

    2015-01-01

    The paper presents the Gamma-4 four-module electrophysical facility project developed for radiation physics research. For this facility, we have developed and tested a typical module which, with a matched load, generates an electrical pulse with voltage and current amplitudes of up to 2 MV and 750 kA, respectively, and with a half-height duration of 60 ns. 700 shots were performed which conformed the operating parameters and reliability of the module. Layouts of the facility for the modes of synchronous (with accuracy of ±3 ns) operation of the modules with vacuum electron diodes and with a current summator to generate soft x-ray pulses have been developed.

  8. The National Ignition Facility project

    SciTech Connect

    Paisner, J.A.; Boyes, J.D.; Kumpan, S.A.; Sorem, M.

    1996-06-01

    The Secretary of the U.S. Department of Energy (DOE) commissioned a Conceptual Design Report (CDR) for the National Ignition Facility (NIF) in January 1993 as part of a Key Decision Zero (KD0), justification of Mission Need. Motivated by the progress to date by the Inertial Confinement Fusion (ICF) program in meeting the Nova Technical Contract goals established by the National Academy of Sciences in 1989, the Secretary requested a design using a solid-state laser driver operating at the third harmonic (0.35 {mu}m) of neodymium (Nd) glass. The participating ICF laboratories signed a Memorandum of Agreement in August 1993, and established a Project organization, including a technical team from the Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Sandia National Laboratories (SNL), and the Laboratory for Laser Energetics at the University of Rochester. Since then, the authors completed the NIF conceptual design, based on standard construction at a generic DOE Defense Program`s site, and issued a 7,000-page, 27-volume CDR in May 1994. Over the course of the conceptual design study, several other key documents were generated, including a Facilities Requirements Document, a Conceptual Design Scope and Plan, a Target Physics Design Document, a Laser Design Cost Basis Document, a Functional Requirements Document, an Experimental Plan for Indirect Drive Ignition, and a Preliminary Hazards Analysis (PHA) Document. DOE used the PHA to categorize the NIF as a low-hazard, non-nuclear facility. This article presents an overview of the NIF project.

  9. Technical Approach and Plan for Transitioning Spent Nuclear Fuel (SNF) Project Facilities to the Environmental Restoration Program

    SciTech Connect

    SKELLY, W.A.

    1999-10-06

    This document describes the approach and process in which the 100-K Area Facilities are to be deactivated and transitioned over to the Environmental Restoration Program after spent nuclear fuel has been removed from the K Basins. It describes the Transition Project's scope and objectives, work breakdown structure, activity planning, estimated cost, and schedule. This report will be utilized as a planning document for project management and control and to communicate details of project content and integration.

  10. Robot Work Platform for Large Hot Cell Deactivation

    SciTech Connect

    BITTEN, E.J.

    2000-05-01

    The 324 Building, located at the Hanford Site near Richland, Washington, is being deactivated to meet state and federal cleanup commitments. The facility is currently in its third year of a nine-year project to complete deactivation and closure for long-term surveillance and maintenance. The 324 building contains large hot cells that were used for high-radiation, high-contamination chemical process development and demonstrations. A major obstacle for the 324 deactivation project is the inability to effectively perform deactivation tasks within highly radioactive, contaminated environments. Current strategies use inefficient, resource intensive technologies that significantly impact the cost and schedule for deactivation. To meet mandated cleanup commitments, there is a need to deploy rapid, more efficient remote/robot technologies to minimize worker exposure, accelerate work tasks, and eliminate the need for multiple specialized tool design and procurement efforts. This paper describes the functions and performance requirements for a crane-deployed remote/robot Work Platform possessing full access capabilities. The remote/robot Work Platform will deploy commercially available off-the-shelf tools and end effectors to support Project cleanup goals and reduce overall project risk and cost. The intent of this system is to maximize the use of off-the-shelf technologies that minimize additional new, unproven, or novel designs. This paper further describes procurement strategy, the selection process, the selected technology, and the current status of the procurement and lessons learned. Funding, in part, has been provided by the US Department of Energy, Office of Science and Technology, Deactivation and Decommissioning Focus Area.

  11. Record of the facility deactivation, decommissioning, and material disposition (D and D) workshop: A new focus for technology development, opportunities for industry/government collaboration

    SciTech Connect

    Bedick, R.C.; Bossart, S.J.; Hart, P.W.

    1995-07-01

    This workshop was held at the Morgantown Energy Technology Center (METC) in Morgantown, West Virginia, on July 11--12, 1995. The workshop sought to establish a foundation for continued dialogue between industry and the DOE to ensure that industry`s experiences, lessons learned, and recommendations are incorporated into D and D program policy, strategy, and plans. The mission of the D and D Focus Area is to develop improved technologies, processes and products, to characterize, deactivate, survey, maintain, decontaminate, dismantle, and dispose of DOE surplus structures, buildings, and contents. The target is a five-to-one return on investment through cost avoidance. The cornerstone of the D and D focus area activities is large-scale demonstration projects that actually decontaminate, decommission, and dispose of a building. The aim is to demonstrate innovative D and D technologies as part of an ongoing DOE D and D project. OTD would pay the incremental cost of demonstrating the innovative technologies. The goal is to have the first demonstration project completed within the next 2 years. The intent is to select projects, or a project, with visible impact so all of the stakeholders know that a building was removed, and demonstrate at a scale that is convincing to the customers in the EM program so they feel comfortable using it in subsequent D and D projects. The plan is to use a D and D integrating contractor who can then use the expertise in this project to use in jobs at other DOE sites.

  12. Facility Interface Capability Assessment (FICA) project report

    SciTech Connect

    Pope, R.B.; MacDonald, R.R.; Viebrock, J.M.; Mote, N.

    1995-09-01

    The US Department of Energy`s (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing the Civilian Radioactive Waste Management System (CRWMS) to accept spent nuclear fuel from commercial facilities. The objective of the Facility Interface Capability Assessment (FICA) project was to assess the capability of each commercial spent nuclear fuel (SNF) storage facility, at which SNF is stored, to handle various SNF shipping casks. The purpose of this report is to present and analyze the results of the facility assessments completed within the FICA project. During Phase 1, the data items required to complete the facility assessments were identified and the database for the project was created. During Phase 2, visits were made to 122 facilities on 76 sites to collect data and information, the database was updated, and assessments of the cask-handling capabilities at each facility were performed. Each assessment of cask-handling capability contains three parts: the current capability of the facility (planning base); the potential enhanced capability if revisions were made to the facility licensing and/or administrative controls; and the potential enhanced capability if limited physical modifications were made to the facility. The main conclusion derived from the planning base assessments is that the current facility capabilities will not allow handling of any of the FICA Casks at 49 of the 122 facilities evaluated. However, consideration of potential revisions and/or modifications showed that all but one of the 49 facilities could be adapted to handle at least one of the FICA Casks. For this to be possible, facility licensing, administrative controls, and/or physical aspects of the facility would need to be modified.

  13. Idaho Waste Vitrification Facilities Project Vitrified Waste Interim Storage Facility

    SciTech Connect

    Bonnema, Bruce Edward

    2001-09-01

    This feasibility study report presents a draft design of the Vitrified Waste Interim Storage Facility (VWISF), which is one of three subprojects of the Idaho Waste Vitrification Facilities (IWVF) project. The primary goal of the IWVF project is to design and construct a treatment process system that will vitrify the sodium-bearing waste (SBW) to a final waste form. The project will consist of three subprojects that include the Waste Collection Tanks Facility, the Waste Vitrification Facility (WVF), and the VWISF. The Waste Collection Tanks Facility will provide for waste collection, feed mixing, and surge storage for SBW and newly generated liquid waste from ongoing operations at the Idaho Nuclear Technology and Engineering Center. The WVF will contain the vitrification process that will mix the waste with glass-forming chemicals or frit and turn the waste into glass. The VWISF will provide a shielded storage facility for the glass until the waste can be disposed at either the Waste Isolation Pilot Plant as mixed transuranic waste or at the future national geological repository as high-level waste glass, pending the outcome of a Waste Incidental to Reprocessing determination, which is currently in progress. A secondary goal is to provide a facility that can be easily modified later to accommodate storage of the vitrified high-level waste calcine. The objective of this study was to determine the feasibility of the VWISF, which would be constructed in compliance with applicable federal, state, and local laws. This project supports the Department of Energy’s Environmental Management missions of safely storing and treating radioactive wastes as well as meeting Federal Facility Compliance commitments made to the State of Idaho.

  14. National Biomedical Tracer Facility: Project definition study

    SciTech Connect

    Heaton, R.; Peterson, E.; Smith, P.

    1995-05-31

    The Los Alamos National Laboratory is an ideal institution and New Mexico is an ideal location for siting the National Biomedical Tracer Facility (NBTF). The essence of the Los Alamos proposal is the development of two complementary irradiation facilities that combined with our existing radiochemical processing hot cell facilities and waste handling and disposal facilities provide a low cost alternative to other proposals that seek to satisfy the objectives of the NBTF. We propose the construction of a 30 MeV cyclotron facility at the site of the radiochemical facilities, and the construction of a 100 MeV target station at LAMPF to satisfy the requirements and objectives of the NBTF. We do not require any modifications to our existing radiochemical processing hot cell facilities or our waste treatment and disposal facilities to accomplish the objectives of the NBTF. The total capital cost for the facility defined by the project definition study is $15.2 M. This cost estimate includes $9.9 M for the cyclotron and associated facility, $2.0 M for the 100 MeV target station at LAMPF, and $3.3 M for design.

  15. The National Ignition Facility Project. Revision 1

    SciTech Connect

    Paisner, J.A.; Campbell, E.M.; Hogan, W.J.

    1994-06-16

    The mission of the National Ignition Facility is to achieve ignition and gain in inertial confinement fusion targets in the laboratory. The facility will be used for defense applications such as weapons physics and weapons effects testing, and for civilian applications such as fusion energy development and fundamental studies of matter at high temperatures and densities. This paper reviews the design, schedule, and costs associated with the construction project.

  16. Fateh Field production facility reconfiguration project

    SciTech Connect

    Dorcheus, S.M.; Landis, S.R.; Robertson, C.A.

    1995-10-01

    Modification of the Dubai Petroleum Co. (DPC) Fateh Field central production facility has reduced wellhead pressures about 10% field-wide, resulting in increased oil production and incremental reserve addition. The facility reconfiguration has reduced operating and maintenance problems experienced with separators and inlet piping, while improving oil recovery. A key challenge of the Reconfiguration Project was to devise a separation scheme which redistributed fluid between vessels, and an installation method which utilized existing equipment to the greatest extent possible, eliminated downtime during facility modification, and minimized investment. Several reconfiguration options were identified and evaluated. The evaluation combined computer simulation results of surface gathering and separation facilities with modeling efforts of the primary Fateh reservoirs. the preferred reconfiguration option was justified on the basis of increased oil uplift associated with the wellhead pressure reduction. The project was successfully completed in mid-January 1994. This paper describes methods used to evaluate the identified options, project planning, and project implementation. Predicted and actual results are given, and key project execution steps are described.

  17. School Facility Projects in Latin America

    ERIC Educational Resources Information Center

    Berk, Jeffrey; de Cassia Alves Vaz, Rita; Honorio, Joao; Baza, Jadille; Origel, Ricardo; Gomez, Fredys

    2004-01-01

    Many Latin American countries are undertaking projects, in line with practices disseminated by PEB, to share school facilities with the local community, to adapt traditional schools for students with disabilities, and to collaborate with private companies to finance educational buildings. The articles below describe current initiatives in five…

  18. PUREX Deactivation Health and Safety documentation

    SciTech Connect

    Dodd, E.N. III

    1995-01-01

    The purpose of the PUREX Deactivation Project is to establish a passively safe and environmentally secure configuration of PUREX at the Hanford Site, and to preserve that configuration for a 10-year horizon. The 10-year horizon is used to predict future maintenance requirements and represents they typical time duration expended to define, authorize, and initiate the follow-on Decontamination and Decommissioning (D&D) activities. This document was prepared to increase attention to worker safety issues during the deactivation project and, as such, identifies the documentation and programs associated with PUREX Deactivation Health and Safety.

  19. UO3 deactivation end point criteria

    SciTech Connect

    Stefanski, L.D.

    1994-10-01

    The UO{sub 3} Deactivation End Point Criteria are necessary to facilitate the transfer of the UO{sub 3} Facility from the Office of Facility Transition and Management (EM-60) to the office of Environmental Restoration (EM-40). The criteria were derived from a logical process for determining end points for the systems and spaces at the UO{sub 3}, Facility based on the objectives, tasks, and expected future uses pertinent to that system or space. Furthermore, the established criteria meets the intent and supports the draft guidance for acceptance criteria prepared by EM-40, {open_quotes}U.S. Department of Energy office of Environmental Restoration (EM-40) Decontamination and Decommissioning Guidance Document (Draft).{close_quotes} For the UO{sub 3} Facility, the overall objective of deactivation is to achieve a safe, stable and environmentally sound condition, suitable for an extended period, as quickly and economically as possible. Once deactivated, the facility is kept in its stable condition by means of a methodical surveillance and maintenance (S&M) program, pending ultimate decontamination and decommissioning (D&D). Deactivation work involves a range of tasks, such as removal of hazardous material, elimination or shielding of radiation fields, partial decontamination to permit access for inspection, installation of monitors and alarms, etc. it is important that the end point of each of these tasks be established clearly and in advance, for the following reasons: (1) End points must be such that the central element of the deactivation objective - to achieve stability - is unquestionably achieved. (2) Much of the deactivation work involves worker exposure to radiation or dangerous materials. This can be minimized by avoiding unnecessary work. (3) Each task is, in effect, competing for resources with other deactivation tasks and other facilities. By assuring that each task is appropriately bounded, DOE`s overall resources can be used most fully and effectively.

  20. Fast Flux Test Facility Closure Project - Project Management Plan

    SciTech Connect

    BEACH, R.R.

    2002-09-26

    The Fast Flux Test Facility (FFTF) Closure Project, Project Management Plan, Revision 5, provides the scope, cost, and schedule to achieve the most cost effective and expeditious closure of the FFTF to an assumed final end-state with the reactor vessel and the containment building, below the 5504 grade level, being entombed in place. Closure will be completed by December 2009 at a cost of $547 million.

  1. National Ignition Facility project acquisition plan

    SciTech Connect

    Callaghan, R.W.

    1996-04-01

    The purpose of this National Ignition Facility Acquisition Plan is to describe the overall procurement strategy planned for the National Ignition Facility (NIF) Project. The scope of the plan describes the procurement activities and acquisition strategy for the following phases of the NIF Project, each of which receives either plant and capital equipment (PACE) or other project cost (OPC) funds: Title 1 and 2 design and Title 3 engineering (PACE); Optics manufacturing facilitization and pilot production (OPC); Convention facility construction (PACE); Procurement, installation, and acceptance testing of equipment (PACE); and Start-up (OPC). Activities that are part of the base Inertial Confinement Fusion (ICF) Program are not included in this plan. The University of California (UC), operating Lawrence Livermore National Laboratory (LLNL) and Los Alamos National Laboratory, and Lockheed-Martin, which operates Sandia National Laboratory (SNL) and the University of Rochester Laboratory for Laser Energetics (UR-LLE), will conduct the acquisition of needed products and services in support of their assigned responsibilities within the NIF Project structure in accordance with their prime contracts with the Department of Energy (DOE). LLNL, designated as the lead Laboratory, will have responsibility for all procurements required for construction, installation, activation, and startup of the NIF.

  2. The rare isotope accelerator (RIA) facility project

    SciTech Connect

    Christoph Leemann

    2000-08-01

    The envisioned Rare-Isotope Accelerator (RIA) facility would add substantially to research opportunities for nuclear physics and astrophysics by combining increased intensities with a greatly expanded variety of high-quality rare-isotope beams. A flexible superconducting driver linac would provide 100 kW, 400 MeV/nucleon beams of any stable isotope from hydrogen to uranium onto production targets. Combinations of projectile fragmentation, target fragmentation, fission, and spallation would produce the needed broad assortment of short-lived secondary beams. This paper describes the project's background, purpose, and status, the envisioned facility, and the key subsystem, the driver linac. RIA's scientific purposes are to advance current theoretical models, reveal new manifestations of nuclear behavior, and probe the limits of nuclear existence [3]. Figures 1 and 2 show, respectively, examples of RIA research opportunities and the yields projected for pursuing them. Figure 3 outlines a conceptual approach for delivering the needed beams.

  3. National Ignition Facility Project Site Safety Program

    SciTech Connect

    Dun, C

    2003-09-30

    This Safety Program for the National Ignition Facility (NIF) presents safety protocols and requirements that management and workers shall follow to assure a safe and healthful work environment during activities performed on the NIF Project site. The NIF Project Site Safety Program (NPSSP) requires that activities at the NIF Project site be performed in accordance with the ''LLNL ES&H Manual'' and the augmented set of controls and processes described in this NIF Project Site Safety Program. Specifically, this document: (1) Defines the fundamental NIF site safety philosophy. (2) Defines the areas covered by this safety program (see Appendix B). (3) Identifies management roles and responsibilities. (4) Defines core safety management processes. (5) Identifies NIF site-specific safety requirements. This NPSSP sets forth the responsibilities, requirements, rules, policies, and regulations for workers involved in work activities performed on the NIF Project site. Workers are required to implement measures to create a universal awareness that promotes safe practice at the work site and will achieve NIF management objectives in preventing accidents and illnesses. ES&H requirements are consistent with the ''LLNL ES&H Manual''. This NPSSP and implementing procedures (e.g., Management Walkabout, special work procedures, etc.,) are a comprehensive safety program that applies to NIF workers on the NIF Project site. The NIF Project site includes the B581/B681 site and support areas shown in Appendix B.

  4. N Reactor Deactivation Program Plan. Revision 4

    SciTech Connect

    Walsh, J.L.

    1993-12-01

    This N Reactor Deactivation Program Plan is structured to provide the basic methodology required to place N Reactor and supporting facilities {center_dot} in a radiologically and environmentally safe condition such that they can be decommissioned at a later date. Deactivation will be in accordance with facility transfer criteria specified in Department of Energy (DOE) and Westinghouse Hanford Company (WHC) guidance. Transition activities primarily involve shutdown and isolation of operational systems and buildings, radiological/hazardous waste cleanup, N Fuel Basin stabilization and environmental stabilization of the facilities. The N Reactor Deactivation Program covers the period FY 1992 through FY 1997. The directive to cease N Reactor preservation and prepare for decommissioning was issued by DOE to WHC on September 20, 1991. The work year and budget data supporting the Work Breakdown Structure in this document are found in the Activity Data Sheets (ADS) and the Environmental Restoration Program Baseline, that are prepared annually.

  5. A PROPOSED FRAMEWORK FOR PLANNING DEACTIVATION AND DECOMMISSIONING ENGINEERING AND DESIGN ACTIVITIES TO MEET THE REQUIREMENTS OF DOE ORDER 413.3A, PROGRAM AND PROJECT MANAGEMENT FOR THE ACQUISITION OF CAPITAL ASSETS

    SciTech Connect

    Santos, J; John Gladden, J

    2007-11-06

    This paper provides guidance in applying the requirements of DOE O 413.3A to Deactivation and Decommissioning (D&D) projects. A list of 41 engineering and design activities relevant to D&D projects was generated. For several activities in this list, examples of the level of development and/or types of deliverables that might be expected at the completion of the conceptual, preliminary and final project design phases described in the Order are provided.

  6. Remote System Technologies for Deactivating Hanford Hot Cells (for WM'03 - abstract included)

    SciTech Connect

    BERLIN, G.T.

    2003-01-28

    Remote system technologies are being deployed by Fluor Hanford to help accelerate the deactivation of highly-radioactive hot cell facilities. This paper highlights the application of several remotely deployed technologies enabling the deactivation tasks.

  7. Iraq nuclear facility dismantlement and disposal project

    SciTech Connect

    Cochran, J.R.; Danneels, J.; Kenagy, W.D.; Phillips, C.J.; Chesser, R.K.

    2007-07-01

    The Al Tuwaitha nuclear complex near Baghdad contains a significant number of nuclear facilities from Saddam Hussein's dictatorship. Because of past military operations, lack of upkeep and looting there is now an enormous radioactive waste problem at Al Tuwaitha. Al Tuwaitha contains uncharacterised radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals. The current security situation in Iraq hampers all aspects of radioactive waste management. Further, Iraq has never had a radioactive waste disposal facility, which means that ever increasing quantities of radioactive waste and material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS has funded the International Atomic Energy Agency (IAEA) to provide technical assistance to the GOI via a Technical Cooperation Project. Program coordination will be provided by the DOS, consistent with U.S. and GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and for providing waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for the vast majority of the implementation of the NDs Program. (authors)

  8. National Ignition Facility Project Execution Plan

    SciTech Connect

    Moses, E

    2000-08-14

    The ''National Ignition Facility (NIF) Justification of Mission Need'', which was approved by the Secretary of Energy in January 1993, defines the mission of the National Inertial Confinement Fusion (ICF) Program and discusses the specific mission of the NIF Project. The NIF experimental capability will allow nuclear-weapons scientists to assess stockpile problems, verify computational tools, test for nuclear-weapons effects, and increase their understanding of weapons physics. The three weapons laboratory directors and the National Nuclear Security Administration (NNSA) Deputy Administrator for Defense Programs have reviewed the role of the NIT; in Stockpile Stewardship in a joint letter. Along with the Accelerated Strategic Computing Initiative numerical simulations and other aboveground experimental facilities, the NIF will provide critical data that will allow the United States to maintain its technical capabilities in nuclear weapons in the absence of underground testing. As a secondary objective, the NIF will advance our understanding of ICF and help to assess its potential as an energy source. Achieving fusion ignition in the NIF will advance both defense and energy objectives. In affirming the Project's Critical Decision 2,* ''Approval of New Start'', the Secretary of Energy verified the mission need and emphasized that the NIF has the potential to contribute significantly to the DOE missions.

  9. Iraq nuclear facility dismantlement and disposal project (NDs Project).

    SciTech Connect

    Cochran, John Russell

    2010-06-01

    The Al Tuwaitha nuclear complex near Baghdad contains a number of facilities from Saddam Hussan's nuclear weapons program. Past military operations, lack of upkeep and looting have created an enormous radioactive waste problem at the Al Tuwaitha complex, which contains various, uncharacterized radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals that must be constantly guarded. Iraq has never had a radioactive waste disposal facility and the lack of a disposal facility means that ever increasing quantities of radioactive material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS is funding the IAEA to provide technical assistance via Technical Cooperation projects. Program coordination will be provided by the DOS, consistent with GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for implementation of the NDs Program.

  10. Facility stabilization project, fiscal year 1998 -- Multi-year workplan (MYWP) for WBS 1.4

    SciTech Connect

    Floberg, W.C.

    1997-09-30

    The primary Facility Stabilization mission is to provide minimum safe surveillance and maintenance of facilities and deactivate facilities on the Hanford Site, to reduce risks to workers, the public and environment, transition the facilities to a low cost, long term surveillance and maintenance state, and to provide safe and secure storage of special nuclear materials, nuclear materials, and nuclear fuel. Facility Stabilization will protect the health and safety of the public and workers, protect the environment and provide beneficial use of the facilities and other resources. Work will be in accordance with the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement), local, national, international and other agreements, and in compliance with all applicable Federal, state, and local laws. The stakeholders will be active participants in the decision processes including establishing priorities, and in developing a consistent set of rules, regulations, and laws. The work will be leveraged with a view of providing positive, lasting economic impact in the region. Effectiveness, efficiency, and discipline in all mission activities will enable Hanford Site to achieve its mission in a continuous and substantive manner. As the mission for Facility Stabilization has shifted from production to support of environmental restoration, each facility is making a transition to support the Site mission. The mission goals include the following: (1) Achieve deactivation of facilities for transfer to EM-40, using Plutonium Uranium Extraction (PUREX) plant deactivation as a model for future facility deactivation; (2) Manage nuclear materials in a safe and secure condition and where appropriate, in accordance with International Atomic Energy Agency (IAEA) safeguards rules; (3) Treat nuclear materials as necessary, and store onsite in long-term interim safe storage awaiting a final disposition decision by US Department of Energy; (4) Implement nuclear materials

  11. National Ignition Facility project acquisition plan revision 1

    SciTech Connect

    Clobes, A.R.

    1996-10-01

    The purpose of this National Ignition Facility Acquisition Plan is to describe the overall procurement strategy planned for the National Ignition Facility M Project. It was prepared for the NIP Prood Office by the NIF Procurement Manager.

  12. Status of the National Ignition Facility project

    SciTech Connect

    Paisner, J.A.; Lowdermilk, W.H.; Boyes, J.D.; Sorem, M.S.; Soures, J.M.

    1997-04-01

    The ultimate goal of worldwide research in inertial confinement fusion (ICF) is to develop fusion as an inexhaustible, economic, environmentally safe source of electric power. Following nearly thirty years of laboratory and underground fusion experiments, the next step toward this goal is to demonstrate ignition and propagating burn of fusion fuel in the laboratory. The National Ignition Facility(NIF) Project is being constructed at Lawrence Livermore National Laboratory (LLNL), for just this purpose. NIF will use advanced Nd-glass laser technology to deliver 1.8 MJ of 0.35-um laser light in a shaped pulse, several nanoseconds in duration, achieving a peak power of 500 TW. A national community of U.S. laboratories is participating in this project, now in its final design phase. Franceand the United Kingdom are collaborating on development of required technology under bilateral agreements with the US. This paper presents thestatus of the laser design and development of its principal components and optical elements.

  13. Education & Collection Facility GSHP Demonstration Project

    SciTech Connect

    Joplin, Jeff

    2015-03-28

    The Denver Museum of Nature & Science (DMNS) designed and implemented an innovative ground source heat pump (GSHP) system for heating and cooling its new Education and Collection Facility (ECF) building addition. The project goal was to successfully design and install an open-loop GSHP system that utilized water circulating within an underground municipal recycled (non-potable) water system as the heat sink/source as a demonstration project. The expected results were to significantly reduce traditional GSHP installation costs while increasing system efficiency, reduce building energy consumption, require significantly less area and capital to install, and be economically implemented wherever access to a recycled water system is available. The project added to the understanding of GSHP technology by implementing the first GSHP system in the United States utilizing a municipal recycled water system as a heat sink/source. The use of this fluid through a GSHP system has not been previously documented. This use application presents a new opportunity for local municipalities to develop and expand the use of underground municipal recycled (non-potable) water systems. The installation costs for this type of technology in the building structure would be a cost savings over traditional GSHP costs, provided the local municipal infrastructure was developed. Additionally, the GSHP system functions as a viable method of heat sink/source as the thermal characteristics of the fluid are generally consistent throughout the year and are efficiently exchanged through the GSHP system and its components. The use of the recycled water system reduces the area required for bore or loop fields; therefore, presenting an application for building structures that have little to no available land use or access. This GSHP application demonstrates the viability of underground municipal recycled (non-potable) water systems as technically achievable, environmentally supportive, and an efficient

  14. Deactivation completed at historic Hanford Fuels Laboratory

    SciTech Connect

    Gerber, M.S.

    1994-03-01

    This report discusses deactivation work which was completed as of March 31, 1994 at the 308 Fuels Development Laboratory (FDL) at the Hanford Site near Richland, Washington. The decision to deactivate the structure, formerly known as the Plutonium Fabrication Pilot Plant (PFPP), was driven by a 1980s Department of Energy (DOE) decision that plutonium fuels should not be fabricated in areas near the Site`s boundaries, as well as by changing facility structural requirements. Inventory transfer has been followed by the cleanout and stabilization of plutonium oxide (PuO{sub 2}) and enriched uranium oxide (UO{sub 2}) residues and powders in the facility`s equipment and duct work. The Hanford Site, located in southeastern Washington state, was one of America`s primary arsenals of nuclear defense production for nearly 50 years beginning in World War II. Approximately 53 metric tons of weapons grade plutonium, over half of the national supply and about one quarter of the world`s supply, were produced at Hanford between 1944 and 1989. Today, many Site buildings are undergoing deactivation, a precursor phase to decontamination and decommissioning (D&D). The primary difference between the two activities is that equipment and structural items are not removed or torn down in deactivation. However, utilities are disconnected, and special nuclear materials (SNM) as well as hazardous and pyrophoric substances are removed from structures undergoing this process.

  15. Vitrification facility at the West Valley Demonstration Project

    SciTech Connect

    DesCamp, V.A.; McMahon, C.L.

    1996-07-01

    This report is a description of the West Valley Demonstration Project`s vitrification facilities from the establishment of the West Valley, NY site as a federal and state cooperative project to the completion of all activities necessary to begin solidification of radioactive waste into glass by vitrification. Topics discussed in this report include the Project`s background, high-level radioactive waste consolidation, vitrification process and component testing, facilities design and construction, waste/glass recipe development, integrated facility testing, and readiness activities for radioactive waste processing.

  16. Project W-049H disposal facility test report

    SciTech Connect

    Buckles, D.I.

    1995-01-01

    The purpose of this Acceptance Test Report (ATR) for the Project W-049H, Treated Effluent Disposal Facility, is to verify that the equipment installed in the Disposal Facility has been installed in accordance with the design documents and function as required by the project criteria.

  17. 308 Building deactivation mission analysis report

    SciTech Connect

    Lund, D.P.

    1995-05-24

    This report presents the results of the 308 Building (Fuels Development Laboratory) Deactivation Project mission analysis. Hanford systems engineering (SE) procedures call for a mission analysis. The mission analysis is an important first step in the SE process. The functions and requirements to successfully accomplish this mission, the selected alternatives and products will later be defined using the SE process.

  18. The Low Temperature Microgravity Physics Facility Project

    NASA Technical Reports Server (NTRS)

    Chui, T.; Holmes, W.; Lai, A.; Croonquist, A.; Eraker, J.; Abbott, R.; Mills, G.; Mohl, J.; Craig, J.; Balachandra, B.; Gannon, J.

    2000-01-01

    We describe the design and development of the Low Temperature Microgravity Physics Facility, which is intended to provide a unique environment of low temperature and microgravity for the scientists to perform breakthrough investigations on board the International Space Station.

  19. National Biomedical Tracer Facility. Project definition study

    SciTech Connect

    Schafer, R.

    1995-02-14

    We request a $25 million government-guaranteed, interest-free loan to be repaid over a 30-year period for construction and initial operations of a cyclotron-based National Biomedical Tracer Facility (NBTF) in North Central Texas. The NBTF will be co-located with a linear accelerator-based commercial radioisotope production facility, funded by the private sector at approximately $28 million. In addition, research radioisotope production by the NBTF will be coordinated through an association with an existing U.S. nuclear reactor center that will produce research and commercial radioisotopes through neutron reactions. The combined facilities will provide the full range of technology for radioisotope production and research: fast neutrons, thermal neutrons, and particle beams (H{sup -}, H{sup +}, and D{sup +}). The proposed NBTF facility includes an 80 MeV, 1 mA H{sup -} cyclotron that will produce proton-induced (neutron deficient) research isotopes.

  20. Yucca Mountain Project Surface Facilities Design

    SciTech Connect

    P.W. McDaniel; N.R. Brown; P.G. Harrington; J.T. Gardiner; L.J. Trautner

    2002-11-20

    With the recent designation of the Yucca Mountain site as a proposed repository for the disposal of commercial spent nuclear fuel, DOE spent nuclear fuel and high- level waste, work is proceeding on the design of surface facilities to receive, unload, and package the waste into waste packages for emplacement in the repository. This paper summarizes recent progress in the design of these surface facilities.

  1. Quality Assurance Project Plan for Facility Effluent Monitoring Plan activities

    SciTech Connect

    Nickels, J.M.

    1991-06-01

    This Quality Assurance Project Plan addresses the quality assurance requirements for the Facility Monitoring Plans of the overall site-wide environmental monitoring plan. This plan specifically applies to the sampling and analysis activities and continuous monitoring performed for all Facility Effluent Monitoring Plan activities conducted by Westinghouse Hanford Company. It is generic in approach and will be implemented in conjunction with the specific requirements of individual Facility Effluent Monitoring Plans. This document is intended to be a basic road map to the Facility Effluent Monitoring Plan documents (i.e., the guidance document for preparing Facility Effluent Monitoring Plans, Facility Effluent Monitoring Plan determinations, management plan, and Facility Effluent Monitoring Plans). The implementing procedures, plans, and instructions are appropriate for the control of effluent monitoring plans requiring compliance with US Department of Energy, US Environmental Protection Agency, state, and local requirements. This Quality Assurance Project Plan contains a matrix of organizational responsibilities, procedural resources from facility or site manuals used in the Facility Effluent Monitoring Plans, and a list of the analytes of interest and analytical methods for each facility preparing a Facility Effluent Monitoring Plan. 44 refs., 1 figs., 2 tabs.

  2. Quality Assurance Project Plan for Facility Effluent Monitoring Plan activities

    SciTech Connect

    Frazier, T.P.

    1994-10-20

    This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the Facility Effluent Monitoring Plans, which are part of the overall Hanford Site Environmental Protection Plan. This plan specifically applies to the sampling and analysis activities and continuous monitoring performed for all Facility Effluent Monitoring Plan activities conducted by Westinghouse Hanford Company. It is generic in approach and will be implemented in conjunction with the specific requirements of the individual Facility Effluent Monitoring Plans.

  3. Project W-441, cold vacuum drying facility design requirements document

    SciTech Connect

    O`Neill, C.T.

    1997-05-08

    This document has been prepared and is being released for Project W-441 to record the design basis for the design of the Cold Vacuum Drying Facility. This document sets forth the physical design criteria, Codes and Standards, and functional requirements that were used in the design of the Cold Vacuum Drying Facility. This document contains section 3, 4, 6, and 9 of the Cold Vacuum Drying Facility Design Requirements Document. The remaining sections will be issued at a later date. The purpose of the Facility is to dry, weld, and inspect the Multi-Canister Overpacks before transport to dry storage.

  4. Sandia National Laboratories participation in the National Ignition Facility project

    SciTech Connect

    Boyes, J.; Boyer, W.; Chael, J.; Cook, D.; Cook, W.; Downey, T.; Hands, J.; Harjes, C.; Leeper, R.; McKay, P.; Micano, P.; Olson, R.; Porter, J.; Quintenz, J.; Roberts, V.; Savage, M.; Simpson, W.; Seth, A.; Smith, R.; Wavrik, M.; Wilson, M.

    1996-08-01

    The National Ignition Facility is a $1.1B DOE Defense Programs Inertial Confinement Fusion facility supporting the Science Based Stockpile Stewardship Program. The goal of the facility is to achieve fusion ignition and modest gain in the laboratory. The NIF project is responsible for the design and construction of the 192 beam, 1.8 MJ laser necessary to meet that goal. - The project is a National project with participation by Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Sandia National Laboratory (SNL), the University of Rochester Laboratory for Laser Energetics (URLLE) and numerous industrial partners. The project is centered at LLNL which has extensive expertise in large solid state lasers. The other partners in the project have negotiated their participation based on the specific expertise they can bring to the project. In some cases, this negotiation resulted in the overall responsibility for a WBS element; in other cases, the participating laboratories have placed individuals in the project in areas that need their individual expertise. The main areas of Sandia`s participation are in the management of the conventional facility design and construction, the design of the power conditioning system, the target chamber system, target diagnostic instruments, data acquisition system and several smaller efforts in the areas of system integration and engineering analysis. Sandia is also contributing to the technology development necessary to support the project by developing the power conditioning system and several target diagnostics, exploring alternate target designs, and by conducting target experiments involving the ``foot`` region of the NIF power pulse. The project has just passed the mid-point of the Title I (preliminary) design phase. This paper will summarize Sandia`s role in supporting the National Ignition Facility and discuss the areas in which Sandia is contributing. 3 figs.

  5. Congressional hearing reviews NSF major research and facilities projects

    NASA Astrophysics Data System (ADS)

    Showstack, Randy

    2012-03-01

    An 8 March congressional hearing about the U.S. National Science Foundation's Major Research Equipment and Facilities Construction (NSF MREFC) account focused on fiscal management and accountability of projects in that account and reviewed concerns raised by NSF's Office of Inspector General (OIG). NSF established the MREFC account in 1995 to better plan and manage investments in major equipment and facilities projects, which can cost from tens of millions to hundreds of millions of dollars, and the foundation has funded 17 MREFC projects since then. The Obama administration's proposed fiscal year (FY) 2013 budget includes funding for four MREFC projects: Advanced Laser Gravitational-Wave Observatory (AdvLIGO), Advanced Technology Solar Telescope (ATST), National Ecological Observatory (NEON), and Ocean Observatories Initiative (OOI). The hearing, held by a subcommittee of the House of Representatives' Committee on Science, Space, and Technology, reviewed management oversight throughout the life cycles of MREFC projects and concerns raised in recent OIG reports about the use of budget contingency funds. NSF's February 2012 manual called "Risk management guide for large facilities" states that cost contingency is "that portion of the project budget required to cover `known unknowns,'" such as planning and estimating errors and omissions, minor labor or material price fluctuations, and design developments and changes within the project scope. Committee members acknowledged measures that NSF has made to improve the MREFC oversight process, but they also urged the agency to continue to take steps to ensure better project management.

  6. Environmental Projects. Volume 9: Construction of hazardous materials storage facilities

    NASA Technical Reports Server (NTRS)

    1989-01-01

    Activities at the Goldstone Deep Space Communications Complex (GDSCC) are carried out in support of seven parabolic dish antennas. These activities may give rise to environmental hazards. This report is one in a series of reports describing environmental projects at GDSCC. The construction of two hazardous materials and wastes storage facilities and an acid-wash facility is described. An overview of the Goldstone complex is also presented along with a description of the environmental aspects of the GDSCC site.

  7. Near-facility environmental monitoring quality assurance project plan

    SciTech Connect

    McKinney, S.M.

    1997-11-24

    This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the preoperational and near facility environmental monitoring performed by Waste Management Federal Services, Inc., Northwest Operations and supersedes WHC-EP-0538-2. This plan applies to all sampling and monitoring activities performed by waste management Federal Services, Inc., Northwest Operations in implementing facility environmental monitoring at the Hanford Site.

  8. Near Facility Environmental Monitoring Quality Assurance Project Plan

    SciTech Connect

    MCKINNEY, S.M.

    2000-05-01

    This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the preoperational and near-facility environmental monitoring directed by Waste Management Technical Services and supersedes HNF-EP-0538-4. This plan applies to all sampling and monitoring activities performed by Waste Management Technical Services in implementing near-facility environmental monitoring at the Hanford Site. This Quality Assurance Project Plan is required by U.S. Department of Energy Order 5400.1 (DOE 1990) as a part of the Environmental Monitoring Plan (DOE-RL 1997) and is used to define: Environmental measurement and sampling locations used to monitor environmental contaminants near active and inactive facilities and waste storage and disposal sites; Procedures and equipment needed to perform the measurement and sampling; Frequency and analyses required for each measurement and sampling location; Minimum detection level and accuracy; Quality assurance components; and Investigation levels. Near-facility environmental monitoring for the Hanford Site is conducted in accordance with the requirements of U.S. Department of Energy Orders 5400.1 (DOE 1990), 5400.5 (DOE 1993), 5484.1 (DOE 1990), and 435.1 (DOE 1999), and DOE/EH-O173T (DOE 1991). It is Waste Management Technical Services' objective to manage and conduct near-facility environmental monitoring activities at the Hanford Site in a cost-effective and environmentally responsible manner that is in compliance with the letter and spirit of these regulations and other environmental regulations, statutes, and standards.

  9. Magnetohydrodynamic projects at the CDIF (Component Development and Integration Facility)

    SciTech Connect

    Not Available

    1990-01-01

    This quarterly technical progress report presents the tasks accomplished at the Component Development and Integration Facility during the fourth quarter of FY90. Areas of technical progress this quarter included: coal system development; seed system development; test bay modification; channel power dissipation and distribution system development; oxygen system storage upgrade; iron core magnet thermal protection system oxygen checkout; TRW slag rejector/CDIF slag removal project; stack gas/environmental compliance upgrade; coal-fired combustor support; 1A channels fabrication and assembly; support of Mississippi State University diagnostic testing; test operations and results; data enhancement; data analysis and modeling; technical papers; and projected activities. 2 tabs.

  10. The Epidaurus Project: holism in Department of Defense health facilities.

    PubMed

    Foote, Frederick

    2012-01-01

    The Epidaurus Project, an advanced initiative in holistic (or whole-person) medicine, has operated in the Military Health System (MHS) since 2001. Its purpose has been to engage prominent civilian authorities on evidence-based building design, family-centered approaches, interdisciplinary care integration, and wellness, to optimize outcomes in the MHS. Over the past decade, many of the Epidaurus idea sets have been incorporated into MHS facility designs and therapeutic programs. The MHS owes a debt of gratitude to the numerous civilian thought leaders who participated in this project. PMID:22338971

  11. Mixed and Low-Level Waste Treatment Facility Project

    SciTech Connect

    Not Available

    1992-04-01

    Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report documents those studies so the project can continue with an evaluation of programmatic options, system tradeoff studies, and the conceptual design phase of the project. This report, appendix B, comprises the engineering design files for this project study. The engineering design files document each waste steam, its characteristics, and identified treatment strategies.

  12. Mixed and Low-Level Waste Treatment Facility project

    SciTech Connect

    Not Available

    1992-04-01

    Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report, Appendix A, Environmental Regulatory Planning Documentation, identifies the regulatory requirements that would be imposed on the operation or construction of a facility designed to process the INEL's waste streams. These requirements are contained in five reports that discuss the following topics: (1) an environmental compliance plan and schedule, (2) National Environmental Policy Act requirements, (3) preliminary siting requirements, (4) regulatory justification for the project, and (5) health and safety criteria.

  13. Safe and Effective Deactivation of Metallic Sodium Filled Scrap and Cold Traps From Sodium-cooled Nuclear Reactor D and D - 12176

    SciTech Connect

    Nester, Dean; Crocker, Ben; Smart, Bill

    2012-07-01

    As part of the Plateau Remediation Project at US Department of Energy's Hanford, Washington site, CH2M Hill Plateau Remediation Company (CHPRC) contracted with IMPACT Services, LLC to receive and deactivate approximately 28 cubic meters of sodium metal contaminated debris from two sodium-cooled research reactors (Enrico Fermi Unit 1 and the Fast Flux Test Facility) which had been stored at Hanford for over 25 years. CHPRC found an off-site team composed of IMPACT Services and Commodore Advanced Sciences, Inc., with the facilities and technological capabilities to safely and effectively perform deactivation of this sodium metal contaminated debris. IMPACT Services provided the licensed fixed facility and the logistical support required to receive, store, and manage the waste materials before treatment, and the characterization, manifesting, and return shipping of the cleaned material after treatment. They also provided a recycle outlet for the liquid sodium hydroxide byproduct resulting from removal of the sodium from reactor parts. Commodore Advanced Sciences, Inc. mobilized their patented AMANDA unit to the IMPACT Services site and operated the unit to perform the sodium removal process. Approximately 816 Kg of metallic sodium were removed and converted to sodium hydroxide, and the project was accomplished in 107 days, from receipt of the first shipment at the IMPACT Services facility to the last outgoing shipment of deactivated scrap metal. There were no safety incidents of any kind during the performance of this project. The AMANDA process has been demonstrated in this project to be both safe and effective for deactivation of sodium and NaK. It has also been used in other venues to treat other highly reactive alkali metals, such as lithium (Li), potassium (K), NaK and Cesium (Cs). (authors)

  14. Nanotube-assisted protein deactivation

    NASA Astrophysics Data System (ADS)

    Joshi, Amit; Punyani, Supriya; Bale, Shyam Sundhar; Yang, Hoichang; Borca-Tasciuc, Theodorian; Kane, Ravi S.

    2008-01-01

    Conjugating proteins onto carbon nanotubes has numerous applications in biosensing, imaging and cellular delivery. However, remotely controlling the activity of proteins in these conjugates has never been demonstrated. Here we show that upon near-infrared irradiation, carbon nanotubes mediate the selective deactivation of proteins in situ by photochemical effects. We designed nanotube-peptide conjugates to selectively destroy the anthrax toxin, and also optically transparent coatings that can self-clean following either visible or near-infrared irradiation. Nanotube-assisted protein deactivation may be broadly applicable to the selective destruction of pathogens and cells, and will have applications ranging from antifouling coatings to functional proteomics.

  15. Deactivator for olefin polymerization catalyst

    SciTech Connect

    Rekers, L.J.; Speca, A.N.; Mayhew, H.W.

    1987-03-10

    A method is described comprising deactivating an olefin polymerization catalyst selected from the group consisting of Ziegler-Natta transition element catalysts and catalysts based on transition metal oxides by contacting the catalyst with a copolymer. The copolymer consists of an alpha-olefin having from 2 to about 12 carbon atoms and an unsaturated ester of a carboxylic acid. The deactivating copolymer is present in an amount such that the molar ratio of the unsaturated ester thereof to the sum of the transition element component of the polymerization catalyst and a cocatalyst for the transition element catalyst is in the range of between about 0.1 and about 6.

  16. Mixed and Low-Level Waste Treatment Facility project

    SciTech Connect

    Not Available

    1992-04-01

    Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. The engineering studies, initiated in July 1991, identified 37 mixed waste streams, and 55 low-level waste streams. This report documents the waste stream information and potential treatment strategies, as well as the regulatory requirements for the Department of Energy-owned treatment facility option. The total report comprises three volumes and two appendices. This report consists of Volume 1, which explains the overall program mission, the guiding assumptions for the engineering studies, and summarizes the waste stream and regulatory information, and Volume 2, the Waste Stream Technical Summary which, encompasses the studies conducted to identify the INEL's waste streams and their potential treatment strategies.

  17. Deactivation and cleanout of the 308 Fuels Laboratory and the 232-Z Incinerator at the Hanford site

    SciTech Connect

    Gerber, M.S.; Bliss, R.J.

    1994-12-01

    This paper describes the deactivation and source term reduction activities conducted over the recent past in two plutonium-contaminated Hanford Site buildings: the 308 Fuels Development Laboratory and the 232-Z Incinerator. Both of these facilities belong to the U.S. Department of Energy, and the projects are unique success stories carried out in direct support of EM-60 functions and requirements. In both cases the buildings, for different reasons, contained unacceptable amounts of plutonium, and were stabilized and placed in a safe, pre-D&D (decontamination and decommissioning) mode. The concept of deactivation as the last step in the operating life of a facility will be discussed. The need for and requirements of EM-60 transition between operations and D&D, the costs savings, techniques, regulations and lessons learned also will be discussed. This paper describes the strategies that led to successful source term reduction: accurate characterization, cooperation among different divisions within DOE and the Hanford Site, attention to regulations (especially unique in this case since the 232-Z Incinerator has been nominated as a Historic Structure to the National Register of Historic Places), and stakeholder concerns involving the proximity of the 308 Building to the Columbia River. The paper also weaves in the history, missions, and plutonium accumulation of the two buildings. The lessons learned are cogent to many other present and future deactivation activities across the DOE complex and indeed across the world.

  18. Large-scale Demonstration and Deployment Project for D&D of Fuel Storage Canals and Associated Facilities at INEEL

    SciTech Connect

    Whitmill, Larry Joseph

    2001-12-01

    The Department of Energy (DOE) Office of Science and Technology (OST), Deactivation and Decommissioning Focus Area (DDFA), sponsored a Large Scale Demonstration and Deployment Project (LSDDP) at the Idaho National Engineering and Environmental Laboratory (INEEL) under management of the DOE National Energy Technology Laboratory (NETL). The INEEL LSDDP is one of several LSDDPs sponsored by DOE. The LSDDP process integrates field demonstrations into actual decontamination and decommissioning (D&D) operations by comparing new or improved technologies against existing baseline technologies using a side-by-side comparison. The goals are (a) to identify technologies that are cheaper, safer, faster, and cleaner (produce less waste), and (b) to incorporate those technologies into D&D baseline operations. The INEEL LSDDP reviewed more than 300 technologies, screened 141, and demonstrated 17. These 17 technologies have been deployed a total of 70 times at facilities other than those where the technology was demonstrated, and 10 have become baseline at the INEEL. Fifteen INEEL D&D needs have been modified or removed from the Needs Management System as a direct result of using these new technologies. Conservatively, the ten-year projected cost savings at the INEEL resulting from use of the technologies demonstrated in this INEEL LSDDP exceeds $39 million dollars.

  19. Status of the Leopard Laser Project in Nevada Terawatt Facility

    NASA Astrophysics Data System (ADS)

    Wiewior, Piotr P.; Astanovitskiy, A.; Aubry, G.; Batie, S.; Caron, J.; Chalyy, O.; Cowan, T.; Haefner, C.; Le Galloudec, B.; Le Galloudec, N.; Macaulay, D.; Nalajala, V.; Pettee, G.; Samek, S.; Stepanenko, Y.; Vesco, J.

    2009-06-01

    Nevada Terawatt Facility (NTF) currently operates a high-intensity laser system—Leopard. NTF already operates a powerful z-pinch device, called Zebra, for plasma and High Energy Density physics research. The unique research opportunities arise from the combination of NTF's terawatt Zebra z-pinch with 50-terawatt-class Leopard laser. This combination also provides opportunities to address fundamental physics of inertial fusion and high energy density physics with intense laser beam. We report on the status, design and architecture of the Leopard laser project. A first experiments carried out with Leopard will be also briefly mentioned.

  20. Environmental Restoration Disposal Facility (Project W-296) Safety Assessment

    SciTech Connect

    Armstrong, D.L.

    1994-08-01

    This Safety Assessment is based on information derived from the Conceptual Design Report for the Environmental Restoration Disposal Facility (DOE/RL 1994) and ancillary documentation developed during the conceptual design phase of Project W-296. The Safety Assessment has been prepared to support the Solid Waste Burial Ground Interim Safety Basis document. The purpose of the Safety Assessment is to provide an evaluation of the design to determine if the process, as proposed, will comply with US Department of Energy (DOE) Limits for radioactive and hazardous material exposures and be acceptable from an overall health and safety standpoint. The evaluation considered affects on the worker, onsite personnel, the public, and the environment.

  1. NOMINATION FOR THE PROJECT MANAGEMENT INSTITUTE (PMI) PROJECT OF THE YEAR AWARD INTEGRATED DISPOSAL FACILITY (IDF)

    SciTech Connect

    MCLELLAN, G.W.

    2007-02-07

    CH2M HILL Hanford Group, Inc. (CH2M HILL) is pleased to nominate the Integrated Disposal Facility (IDF) project for the Project Management Institute's consideration as 2007 Project of the Year, Built for the U.S, Department of Energy's (DOE) Office of River Protection (ORP) at the Hanford Site, the IDF is the site's first Resource Conservation and Recovery Act (RCRA)-compliant disposal facility. The IDF is important to DOE's waste management strategy for the site. Effective management of the IDF project contributed to the project's success. The project was carefully managed to meet three Tri-Party Agreement (TPA) milestones. The completed facility fully satisfied the needs and expectations of the client, regulators and stakeholders. Ultimately, the project, initially estimated to require 48 months and $33.9 million to build, was completed four months ahead of schedule and $11.1 million under budget. DOE directed construction of the IDF to provide additional capacity for disposing of low-level radioactive and mixed (i.e., radioactive and hazardous) solid waste. The facility needed to comply with federal and Washington State environmental laws and meet TPA milestones. The facility had to accommodate over one million cubic yards of the waste material, including immobilized low-activity waste packages from the Waste Treatment Plant (WTP), low-level and mixed low-level waste from WTP failed melters, and alternative immobilized low-activity waste forms, such as bulk-vitrified waste. CH2M HILL designed and constructed a disposal facility with a redundant system of containment barriers and a sophisticated leak-detection system. Built on a 168-area, the facility's construction met all regulatory requirements. The facility's containment system actually exceeds the state's environmental requirements for a hazardous waste landfill. Effective management of the IDF construction project required working through highly political and legal issues as well as challenges with

  2. Remote System Technologies for Deactivating Hanford Hot Cells

    SciTech Connect

    Berlin, G.; Walton, T.

    2003-02-25

    Remote system technologies are being deployed by Fluor Hanford to help accelerate the deactivation of highly-radioactive hot cell facilities. These technologies offer improved methods for accessing difficult-to-reach spaces and performing tasks such as visual inspection, radiological characterization, decontamination, waste handling, and size reduction. This paper is focused on the application of remote systems in support of deactivation work being performed in several legacy facilities at Hanford (i.e., the 324 and 327 Buildings). These facilities were previously used for fuel fabrication, materials examination, and the development of waste treatment processes. The technologies described in this paper represent significant improvements to Hanford's baseline methods, and may offer benefits to other U.S. Department of Energy (DOE) sites and commercial operations.

  3. Family Mode Deactivation Therapy Results and Implications

    ERIC Educational Resources Information Center

    Apsche, Jack A.; Bass, Christopher K.

    2006-01-01

    This article highlights the inclusion of Mode Deactivation Therapy as a treatment modality for families in crisis. As an empirically validated treatment, Mode Deactivation Therapy has been effective in treating a wide variety of psychological issues. Mode Deactivation Therapy, (MDT) was developed to treat adolescents with disorders of conduct…

  4. Mission Need Statement: Idaho Spent Fuel Facility Project

    SciTech Connect

    Barbara Beller

    2007-09-01

    Approval is requested based on the information in this Mission Need Statement for The Department of Energy, Idaho Operations Office (DOE-ID) to develop a project in support of the mission established by the Office of Environmental Management to "complete the safe cleanup of the environmental legacy brought about from five decades of nuclear weapons development and government-sponsored nuclear energy research". DOE-ID requests approval to develop the Idaho Spent Fuel Facility Project that is required to implement the Department of Energy's decision for final disposition of spent nuclear fuel in the Geologic Repository at Yucca Mountain. The capability that is required to prepare Spent Nuclear Fuel for transportation and disposal outside the State of Idaho includes characterization, conditioning, packaging, onsite interim storage, and shipping cask loading to complete shipments by January 1,2035. These capabilities do not currently exist in Idaho.

  5. Project management plan, Waste Receiving and Processing Facility, Module 1, Project W-026

    SciTech Connect

    Starkey, J.G.

    1993-05-01

    The Hanford Waste Receiving and Processing Facility Module 1 Project (WRAP 1) has been established to support the retrieval and final disposal of approximately 400K grams of plutonium and quantities of hazardous components currently stored in drums at the Hanford Site.

  6. Deactivation by carbon of iron catalysts for indirect liquefaction

    SciTech Connect

    Bartholomew, C.H.

    1991-01-10

    Although promoted cobalt and iron catalysts for Fischer-Tropsch (FT) synthesis of gasoline feedstock were first developed more than three decades ago, a major technical problem still limiting the commercial use of these catalysts today is carbon deactivation. This report describes recent progress in a fundamental, three-year investigation of carbon formation and its effects on the activity and selectivity of promoted iron catalysts for FT synthesis, the objectives of which are to: determine rates and mechanisms of carbon deactivation of unsupported Fe and Fe/K catalysts during CO hydrogenation over a range of CO concentrations, CO:H{sub 2} ratios, and temperatures; and model the rates of deactivation of the same catalysts in fixed-bed reactors. To accomplish the above objectives, the project is divided into the following tasks: (1) determine the kinetics of reaction and of carbon deactivation during CO hydrogenation on Fe and Fe/K catalysts coated on monolith bodies. (2) Determine the reactivities and types of carbon deposited during reaction on the same catalysts from temperature-programmed-surface-reaction spectroscopy (TPSR) and transmission electron microscopy (TEM). Determine the types of iron carbides formed at various temperatures and H{sub 2}/CO ratios using x-ray diffraction and Moessbauer spectroscopy. (3) Develop mathematical deactivation models which include heat and mass transport contributions for FT synthesis is packed-bed reactors. Progress to date is described. 48 refs., 3 figs., 1 tab.

  7. F-Canyon Suspension and Deactivation Safety Analysis Reports

    SciTech Connect

    LOW, JM

    2004-04-30

    This paper describes Savannah River Site's compliance with the Department of Energy (DOE) direction to suspend current operations, transition to accommodate revised facility missions, and initiate operations to deactivate F-Canyon using a suspension and deactivation safety basis. This paper integrates multiple Workshop theme topics - Lessons Learned from the Safety Analysis Process, Improvements in Documenting Hazard and Accident Analysis, and Closure Issues - Decontamination and Decommissioning. The paper describes the process used to develop safety documentation to support suspension and deactivation activities for F-Canyon. Embodied are descriptive efforts that include development of intermediate and final ''end states'' (e.g., transitional operations), preparation of safety bases documents to support transition, performance of suspension and deactivation activities (e.g. solvent washing, tank/sump flushing, and laboratory waste processing), and downgrade of Safety Class and Safety Significant equipment. The reduction and/or removal of hazards in the facility result in significant risk (frequency times consequence) reduction to the public, site workers, and the environment. Risk reduction then allows the downgrade of safety class and safety significant systems (e.g., ventilation system) and elimination of associated surveillances. The downgrade of safety systems results in significant cost savings.

  8. National Biomedical Tracer Facility (NBTF). Project definition study: Phase I

    SciTech Connect

    Lagunas-Solar, M.C.

    1995-02-15

    This report describes a five-year plan for the construction and commissioning of a reliable and versatile NBTF facility for the production of high-quality, high-yield radioisotopes for research, biomedical, and industrial applications. The report is organized in nine sections providing, in consecutive order, responses to the nine questions posed by the U.S. Department of Energy in its solicitation for the NBTF Project Definition Study. In order to preserve direct correspondence (e.g., Sec. 3 = 3rd item), this Introduction is numbered {open_quotes}0.{close_quotes} Accelerator and facility designs are covered in Section 1 (Accelerator Design) and Section 2 (Facility Design). Preliminary estimates of capital costs are detailed in Section 3 (Design and Construction Costs). Full licensing requirements, including federal, state, and local ordinances, are discussed in Section 4 (Permits). A plan for the management of hazardous materials to be generated by NBTF is presented in Section 5 (Waste Management). An evaluation of NBTF`s economic viability and its potential market impact is detailed in Section 6(Business Plan), and is complemented by the plans in Section 7 (Operating Plan) and Section 8 (Radioisotope Plan). Finally, a plan for NBTF`s research, education, and outreach programs is presented in Section 9 (Research and Education Programs).

  9. The radioactive ion beams facility project for the legnaro laboratories

    NASA Astrophysics Data System (ADS)

    Tecchio, Luigi B.

    1999-04-01

    In the frame work of the Italian participation to the project of a high intensity proton facility for the energy amplifier and nuclear waste transmutations, LNL is involving in the design and construction of prototypes of the injection system of the 1 GeV linac that consists of a RFQ (5 MeV, 30 mA) followed by a 100 MeV linac. This program has been already financially supported and the work is actually in progress. In this context, the LNL has been proposed a project for the construction of a second generation facility for the production of radioactive ion beams (RIBs) by using the ISOL method. The final goal consists in the production of neutron rich RIBs with masses ranging from 80 to 160 by using primary beams of protons, deuterons and light ions with energy of 100 MeV and 100 kW power. This project is proposed to be developed in about 10 years from now and intermediate milestones and experiments are foreseen and under consideration for the next INFN five year plan (1999-2003). In such period of time is proposed the construction of a proton/deuteron accelerator of 10 MeV energy and 10 mA current, consisting of a RFQ (5 MeV, 30 mA) and a linac (10 MeV, 10 mA), and of a neutron area dedicated to the RIBs production, to the BNCT applications and to the neutron physics. Some remarks on the production methods will be presented. The possibility of producing radioisotopes by means of the fission induced by neutrons will be investigated and the methods of production of neutrons will be discussed.

  10. Final Design Report for the RH LLW Disposal Facility (RDF) Project

    SciTech Connect

    Austad, S. L.

    2015-05-01

    The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.

  11. Final Design Report for the RH LLW Disposal Facility (RDF) Project

    SciTech Connect

    Austad, Stephanie Lee

    2015-09-01

    The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.

  12. Functional description of the West Valley Demonstration Project Vitrification Facility

    SciTech Connect

    Borisch, R.R.; McMahon, C.L.

    1990-07-01

    The primary objective of the West Valley Demonstration Project (WVDP) is the solidification of approximately 2.1 million liters (560,000 gallons) of high-level radioactive waste (HLW) which resulted from the operation of a nuclear fuel reprocessing plant. Since the original plant was not built to accommodate the processing of waste beyond storage in underground tanks, HLW solidification by vitrification presented numerous engineering challenges. Existing facilities required redesign and conversion to meet their new purpose. Vitrification technology and systems needed to be created and then tested. Equipment modifications, identified from cold test results, were incorporated into the final equipment configuration to be used for radioactive (hot) operations. Cold operations have defined the correct sequence and optimal functioning of the equipment to be used for vitrification and have verified the process by which waste will be solidified into borosilicate glass.

  13. National Ignition Facility Project Site Safety Program Appendix A

    SciTech Connect

    Moses, E

    2001-09-30

    These rules apply to all National Ignition Facility (NIF) workers (workers), which include Lawrence Livermore National Laboratory (LLNL) employees, non-LLNL employees (including contract labor, supplemental labor, vendors, personnel matrixed/assigned from other national laboratories, participating guests, visitors and students) and contractors/subcontractors. The General Rules and NIF Code of Safe Practices shall be used by management to promote the prevention of incidents through indoctrination, safety and health training, and on-the-job application. As a condition for contract award, all employers shall conduct an orientation for all newly hired and rehired employees before those workers will be permitted to start work in this facility. This orientation shall include a discussion of the following information. The General Rules and NIF Code of Safe Practices must be posted at a conspicuous location at the job site office or be provided to each supervisory worker who shall have it readily available. Copies of the General Rules and NIF Code of Safe Practices can also be included in employee safety pamphlets. The Environmental, Safety, and Health (ES&H) rules at the NIF Project site are based upon compliance with the most stringent of Department of Energy (DOE), LLNL, Federal Occupational Safety and Health Administration (OSHA), California (Cal)/OSHA, and federal and state environmental requirements.

  14. Transition projects FY 1995 multi-year program/fiscal year work plan WBS 1.3.1. and 7.1

    SciTech Connect

    Not Available

    1994-09-01

    The primary Transition Projects mission is to deactivate facilities on the Hanford site, in preparation for decontamination and decommissioning, and secondarily to provide safe and secure storage of special nuclear materials, nuclear materials, and nuclear fuel. Transition projects will protect the health and safety of the public and of workers, protect the environment, and provide beneficial use of the facilities and other resources. Goals include the following: Achieve deactivation of facilities for transfer to the Hanford Surplus Facility Program, suing PUREX plant deactivation as a model; Achieve excellence in the conduct of operations and maintenance of nuclear facilities in support of the Hanford Site Mission; manage nuclear materials in a safe and secure condition; treat nuclear materials as necessary and store onsite in long-term interim safe storage awaiting a final disposition decision. Description of the program and projects is included.

  15. Tritium Facilities Modernization and Consolidation Project Process Waste Assessment (Project S-7726)

    SciTech Connect

    Hsu, R.H.; Oji, L.N.

    1997-11-14

    Under the Tritium Facility Modernization {ampersand} Consolidation (TFM{ampersand}C) Project (S-7726) at the Savannah River Site (SS), all tritium processing operations in Building 232-H, with the exception of extraction and obsolete/abandoned systems, will be reestablished in Building 233-H. These operations include hydrogen isotopic separation, loading and unloading of tritium shipping and storage containers, tritium recovery from zeolite beds, and stripping of nitrogen flush gas to remove tritium prior to stack discharge. The scope of the TFM{ampersand}C Project also provides for a new replacement R&D tritium test manifold in 233-H, upgrading of the 233- H Purge Stripper and 233-H/234-H building HVAC, a new 234-H motor control center equipment building and relocating 232-H Materials Test Facility metallurgical laboratories (met labs), flow tester and life storage program environment chambers to 234-H.

  16. Spent Nuclear Fuel (SNF) Project Execution Plan

    SciTech Connect

    LEROY, P.G.

    2000-11-03

    The Spent Nuclear Fuel (SNF) Project supports the Hanford Site Mission to cleanup the Site by providing safe, economic, environmentally sound management of Site spent nuclear fuel in a manner that reduces hazards by staging it to interim onsite storage and deactivates the 100 K Area facilities.

  17. DRAINING HAZARDOUS FLUIDS DURING BUILDING 221-1F DEACTIVATION AT THE SAVANNAH RIVER SITE

    SciTech Connect

    Musall, J.

    2010-05-11

    Several years ago, SRS completed a four year mission to decommission {approx}250 excess facilities. As part of that effort, SRS deactivated multiple facilities (e.g. Building 247-F, Naval Fuels Facility, and Building 211-F, Outside Facilities for F-Canyon) that contained extensive piping systems filled with hazardous material (e.g. nitric acid). Draining of hazardous materials from piping was successfully completed in all facilities without incident. In early 2009, the decommissioning program at SRS was restarted as a result of funding made available by the American Recovery & Reinvestment Act (ARRA). Under ARRA, draining of piping containing hazardous material was initiated in multiple facilities including Building 221-1F (or A-Line). This paper describes and reviews the draining of piping containing hazardous materials at A-Line, with emphasis on an incident involving the draining of nitric acid. The paper is intended to be a resource for engineers, planners, and project managers, who face similar draining challenges.

  18. 75 FR 39926 - Deer Creek Station Energy Facility Project (DOE/EIS-0415)

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-07-13

    ...The Western Area Power Administration (Western) received a request from Basin Electric Power Cooperative (Basin Electric) to interconnect its proposed Deer Creek Station Energy Facility Project (Project) to Western's transmission system. Basin Electric's Project includes the construction of a new 300-megawatt (MW) natural gas-fired combined-cycle generation facility in Brookings County, South......

  19. Deactivation of the EBR-II complex

    SciTech Connect

    Michelbacher, J.A.; Earle, O.K.; Henslee, S.P.

    1997-12-31

    In January of 1994, the Department of Energy mandated the termination of the Integral Fast Reactor (IFR) Program, effective October 1, 1994. To comply with this decision, Argonne National Laboratory-West (ANL-W) prepared a plan providing detailed requirements to place the Experimental Breeder Reactor-II (EBR-II) in a radiologically and industrially safe condition, including removal of all irradiated fuel assemblies from the reactor plant, and removal and stabilization of the primary and secondary sodium, a liquid metal used to transfer heat within the reactor plant. The ultimate goal of the deactivation process is to place the EBR-II complex in a stable condition until a decontamination and decommissioning (D&D) plan can be prepared, thereby minimizing requirements for maintenance and surveillance and maximizing the amount of time for radioactive decay. The final closure state will be achieved in full compliance with federal, state and local environmental, safety, and health regulations and requirements. The decision to delay the development of a detailed D&D plan has necessitated this current action. The EBR-II is a pool-type reactor. The primary system contains approximately 87,000 gallons of sodium, while the secondary system has 13,000 gallons. In order to properly dispose of the sodium in compliance with the Resource Conservation and Recovery Act (RCRA), a facility has been built to react the sodium to a dry carbonate powder in a two stage process. Deactivation of a liquid metal fast breeder reactor (LMFBR) presents unique concerns. Residual amounts of sodium remaining in the primary and secondary systems must be either reacted or inerted to preclude future concerns with sodium-air reactions that generate explosive mixtures of hydrogen and leave corrosive compounds. Residual amounts of sodium on components will effectively {open_quotes}solder{close_quotes} components in place, making future operation or removal unfeasible.

  20. The NTF as a national facility. [project planning

    NASA Technical Reports Server (NTRS)

    Nicks, O. W.

    1977-01-01

    Activities which led to the definition of the National Transonic Facility and the general agreements reached regarding its use and operations are reviewed. Topics discussed include: redefinition of test requirements, development of low cost options, consideration of a single transonic facility using existing hardware if feasible, facility concept recommendations, and acquisition schedule proposals.

  1. Nuclear fuel reprocessing deactivation plan for the Idaho Chemical Processing Plant, Revision 1

    SciTech Connect

    Patterson, M.W.

    1994-10-01

    The decision was announced on April 28, 1992 to cease all United States Department of Energy (DOE) reprocessing of nuclear fuels. This decision leads to the deactivation of all fuels dissolution, solvent extraction, krypton gas recovery operations, and product denitration at the Idaho Chemical Processing Plant (ICPP). The reprocessing facilities will be converted to a safe and stable shutdown condition awaiting future alternate uses or decontamination and decommissioning (D&D). This ICPP Deactivation Plan includes the scope of work, schedule, costs, and associated staffing levels necessary to achieve a safe and orderly deactivation of reprocessing activities and the Waste Calcining Facility (WCF). Deactivation activities primarily involve shutdown of operating systems and buildings, fissile and hazardous material removal, and related activities. A minimum required level of continued surveillance and maintenance is planned for each facility/process system to ensure necessary environmental, health, and safety margins are maintained and to support ongoing operations for ICPP facilities that are not being deactivated. Management of the ICPP was transferred from Westinghouse Idaho Nuclear Company, Inc. (WINCO) to Lockheed Idaho Technologies Company (LITCO) on October 1, 1994 as part of the INEL consolidated contract. This revision of the deactivation plan (formerly the Nuclear Fuel Reprocessing Phaseout Plan for the ICPP) is being published during the consolidation of the INEL site-wide contract and the information presented here is current as of October 31, 1994. LITCO has adopted the existing plans for the deactivation of ICPP reprocessing facilities and the plans developed under WINCO are still being actively pursued, although the change in management may result in changes which have not yet been identified. Accordingly, the contents of this plan are subject to revision.

  2. Mixed and Low-Level Treatment Facility Project

    SciTech Connect

    Not Available

    1992-04-01

    This appendix contains the mixed and low-level waste engineering design files (EDFS) documenting each low-level and mixed waste stream investigated during preengineering studies for Mixed and Low-Level Waste Treatment Facility Project. The EDFs provide background information on mixed and low-level waste generated at the Idaho National Engineering Laboratory. They identify, characterize, and provide treatment strategies for the waste streams. Mixed waste is waste containing both radioactive and hazardous components as defined by the Atomic Energy Act and the Resource Conservation and Recovery Act, respectively. Low-level waste is waste that contains radioactivity and is not classified as high-level waste, transuranic waste, spent nuclear fuel, or 11e(2) byproduct material as defined by DOE 5820.2A. Test specimens of fissionable material irradiated for research and development only, and not for the production of power or plutonium, may be classified as low-level waste, provided the concentration of transuranic is less than 100 nCi/g. This appendix is a tool that clarifies presentation format for the EDFS. The EDFs contain waste stream characterization data and potential treatment strategies that will facilitate system tradeoff studies and conceptual design development. A total of 43 mixed waste and 55 low-level waste EDFs are provided.

  3. Treatment Facility F: Accelerated Removal and Validation Project

    SciTech Connect

    Sweeney, J.J.; Buettner, M.H.; Carrigan, C.R.

    1994-04-01

    The Accelerated Removal and Validation (ARV) phase of remediation at the Treatment Facility F (TFF) site at Lawrence Livermore National Laboratory (LLNL) was designed to accelerate removal of gasoline from the site when compared to normal, single shift, pump-and-treat operations. The intent was to take advantage of the in-place infrastructure plus the increased underground temperatures resulting from the Dynamic Underground Stripping Demonstration Project (DUSDP). Operations continued 24-hours (h) per day between October 4 and December 12, 1993. Three contaminant removal rate enhancement approaches were explored during the period of continuous operation. First, we tried several configurations of the vapor pumping system to maximize the contaminant removal rate. Second, we conducted two brief trials of air injection into the lower steam zone. Results were compared with computer models, and the process was assessed for contaminant removal rate enhancement. Third, we installed equipment to provide additional electrical heating of contaminated low-permeability soil. Four new electrodes were connected into the power system. Diagnostic capabilities at the TFF site were upgraded so that we could safely monitor electrical currents, soil temperatures, and water treatment system processes while approximately 300 kW of electrical energy was being applied to the subsurface.

  4. Overview of the NASA Dryden Flight Research Facility aeronautical flight projects

    NASA Technical Reports Server (NTRS)

    Meyer, Robert R., Jr.

    1992-01-01

    Several principal aerodynamics flight projects of the NASA Dryden Flight Research Facility are discussed. Key vehicle technology areas from a wide range of flight vehicles are highlighted. These areas include flight research data obtained for ground facility and computation correlation, applied research in areas not well suited to ground facilities (wind tunnels), and concept demonstration.

  5. DEACTIVATION AND DECOMMISSIONING ENVIRONMENTAL STRATEGY FOR THE PLUTONIUM FINISHING PLANT COMPLEX, HANFORD NUCLEAR RESERVATION

    SciTech Connect

    Hopkins, A.M.; Heineman, R.; Norton, S.; Miller, M.; Oates, L.

    2003-02-27

    Maintaining compliance with environmental regulatory requirements is a significant priority in successful completion of the Plutonium Finishing Plant (PFP) Nuclear Material Stabilization (NMS) Project. To ensure regulatory compliance throughout the deactivation and decommissioning of the PFP complex, an environmental regulatory strategy was developed. The overall goal of this strategy is to comply with all applicable environmental laws and regulations and/or compliance agreements during PFP stabilization, deactivation, and eventual dismantlement. Significant environmental drivers for the PFP Nuclear Material Stabilization Project include the Tri-Party Agreement; the Resource Conservation and Recovery Act of 1976 (RCRA); the Comprehensive Environmental Response, Compensation and Liability Act of 1980 (CERCLA); the National Environmental Policy Act of 1969 (NEPA); the National Historic Preservation Act (NHPA); the Clean Air Act (CAA), and the Clean Water Act (CWA). Recent TPA negotiation s with Ecology and EPA have resulted in milestones that support the use of CERCLA as the primary statutory framework for decommissioning PFP. Milestones have been negotiated to support the preparation of Engineering Evaluations/Cost Analyses for decommissioning major PFP buildings. Specifically, CERCLA EE/CA(s) are anticipated for the following scopes of work: Settling Tank 241-Z-361, the 232-Z Incinerator, , the process facilities (eg, 234-5Z, 242, 236) and the process facility support buildings. These CERCLA EE/CA(s) are for the purpose of analyzing the appropriateness of the slab-on-grade endpoint Additionally, agreement was reached on performing an evaluation of actions necessary to address below-grade structures or other structures remaining after completion of the decommissioning of PFP. Remaining CERCLA actions will be integrated with other Central Plateau activities at the Hanford site.

  6. Conceptual design report, Sodium Storage Facility, Fast Flux Test Facility, Project F-031

    SciTech Connect

    Shank, D.R.

    1995-02-14

    The Sodium Storage Facility Conceptual Design Report provides conceptual design for construction of a new facility for storage of the 260,000 gallons of sodium presently in the FFTF plant. The facility will accept the molten sodium transferred from the FFTF sodium systems, and store the sodium in a solid state under an inert cover gas until such time as a Sodium Reaction Facility is available for final disposal of the sodium.

  7. Acid phosphatase deactivation by a series mechanism.

    PubMed

    Gianfreda, L; Marrucci, G; Grizzuti, N; Greco, G

    1984-05-01

    Acid phosphatase (E.C.3.1.3.2.) thermal deactivation at pH 3.77 has been investigated by monitoring the enzyme activity as a function of time in the hydrolysis of p-nitrophenyl phosphate. The experimental curves obtained show a two-slope behavior in a log (activity)versus-time plot, which indicates that deactivation occurs via a complex mechanism. From the dependence of the kinetic parameters on both deactivation and hydrolysis temperatures, it is inferred that the deactivation mechanism involves intermediate, temperature-dependent, less-active forms of the enzyme. This interpretation is confirmed by the results of additional tests in which the temperature was suddenly changed during the deactivation process. PMID:18553349

  8. Application of decision analysis to forest road deactivation in unstable terrain.

    PubMed

    Allison, Clay; Sidle, Roy C; Tait, David

    2004-02-01

    Resource managers require objective methodologies to optimize decisions related to forest road deactivation and other aspects of road management, especially in steep terrain, where road-related slope failures inflict extensive environmental damage. Decision analysis represents a systematic framework that clearly identifies real options and critical decision points. This framework links current decisions with expected future outcomes and provides advantages such as a common currency to systematically explore the liability consequences of limited budget expenditures to road deactivation and other road-related activities. Furthermore, the decision framework prevents the analysis from becoming hopelessly entangled by the vast number of possibilities generated by the alternative occurrences, magnitudes, and consequences of landslide/debris flow events and provides the information required for the first step of an adaptive management process. Here, a structured analysis of potential environmental risks for a road deactivation project in coastal British Columbia, Canada is presented. The application of decision analysis generates a ranking of the expected benefits of proposed deactivation activities on various road sections. The ranking distinguishes between road sections that offer high expected benefit from those that offer moderate to low expected benefit. Seventeen of 171, 100-m road segments accounted for 18% of the cumulative cost and 98% of the cumulative expected net benefits from road deactivation. Furthermore, the cost of deactivating a section of road is related to the expected benefit from such deactivation, thus providing the basis for more effective resource allocation and budgeting decisions. PMID:15285396

  9. Goddard Space Flight Center Spacecraft Magnetic Test Facility Restoration Project

    NASA Technical Reports Server (NTRS)

    Vernier, Robert; Bonalksy, Todd; Slavin, James

    2004-01-01

    The Goddard Space Flight Center Spacecraft Magnetic Test Facility (SMTF) was constructed in the 1960's for the purpose of simulating geomagnetic and interplanetary magnetic field environments. The facility includes a three axis Braunbek coil system consisting of 12 loops, 4 loops on each of the three orthogonal axes; a remote earth field sensing magnetometer and servo control building; and a remote power control and instrumentation building. The inner coils are 42-foot in diameter and a 10-foot by 10-foot opening through the outer coils accommodates spacecraft access to the test volume. The physical size and precision of the facility are matched by only two other such facilities in the world. The facility was used extensively from the late 1960's until the early 1990's when the requirement for spacecraft level testing diminished. New NASA missions planned under the Living with a Star, Solar Terrestrial Probes, Explorer, and New Millennium Programs include precision, high-resolution magnetometers to obtain magnetic field data that is critical to fulfilling their scientific mission. It is highly likely that future Lunar and Martian exploration missions will also use precision magnetometers to conduct geophysical magnetic surveys. To ensure the success of these missions ground testing using a magnetic test facility such as the GSFC SMTF will be required. This paper describes the history of the facility, the future mission requirements that have renewed the need for spacecraft level magnetic testing, and the plans for restoring the facility to be capable of performing to its original design specifications.

  10. Spent nuclear fuel project cold vacuum drying facility operations manual

    SciTech Connect

    IRWIN, J.J.

    1999-05-12

    This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

  11. Goddard Space Flight Center Spacecraft Magnetic Test Facility Restoration Project

    NASA Technical Reports Server (NTRS)

    Vernier, Robert; Bonalksy, Todd; Slavin, James

    2004-01-01

    The Goddard Space Flight Center Spacecraft Magnetic Test Facility (SMTF) was constructed in the 1960's for the purpose of simulating geomagnetic and interplanetary magnetic field environments. The facility includes a three axis Braunbek coil system consisting of 12 loops, 4 loops on each of the three orthogonal axes; a remote Earth field sensing magnetometer and servo controller; and a remote power control and instrumentation building. The inner coils of the Braunbek system are 42-foot in diameter with a 10-foot by 10-foot opening through the outer coils to accommodate spacecraft access into the test volume. The physical size and precision of the facility are matched by only two other such facilities in the world. The facility was used extensively from the late 1960's until the early 1990's when the requirement for spacecraft level testing diminished. New NASA missions planned under the Living with a Star, Solar Terrestrial Probes, Explorer, and New Millennium Programs include precision, high-resolution magnetometers to obtain magnetic field data that is critical to fulfilling their scientific mission. It is highly likely that future Lunar and Martian exploration missions will also use precision magnetometers to conduct geophysical magnetic surveys. To ensure the success of these missions, ground-testing using a magnetic test facility such as the GSFC SMTF will be required. This paper describes the history of the facility, the future mission requirements that have renewed the need for spacecraft level magnetic testing, and the plans for restoring the facility to be capable of performing to its original design specifications.

  12. Goddard Space Flight Center Spacecraft Magnetic Test Facility Restoration Project

    NASA Technical Reports Server (NTRS)

    Vernier, Robert; Bonalosky, Todd; Slavin, James

    2004-01-01

    The Goddard Space Flight Center Spacecraft Magnetic Test Facility (SMTF) was constructed in the 1960's for the purpose of simulating geomagnetic and interplanetary magnetic field environments. The facility includes a three axis Braunbek coil system consisting of 12 loops, 4 loops on each of the three orthogonal axes; a remote Earth field sensing magnetometer and servo controller; and a remote power control and instrumentation building. The inner coils of the Braunbek system are 42-foot in diameter with a 10-foot by 10-foot opening through the outer coils to accommodate spacecraft access into the test volume. The physical size and precision of the facility are matched by only two other such facilities in the world. The facility was used extensively from the late 1960's until the early 1990's when the requirement for spacecraft level testing diminished. New NASA missions planned under the Living with a Star, Solar Terrestrial Probes, Explorer, and New Millennium Programs include precision, high-resolution magnetometers to obtain magnetic field data that is critical to fulfilling their scientific mission. It is highly likely that future Lunar and Martian exploration missions will also use precision magnetometers to conduct geophysical magnetic surveys. To ensure the success of these missions, ground testing using a magnetic test facility such as the GSFC SMTF will be required. This paper describes the history of the facility, the future mission requirements that have renewed the need for spacecraft level magnetic testing, and the plans for restoring the facility to be capable of performing to its original design specifications.

  13. Status Review of Wildlife Mitigation, Columbia Basin Hydroelectric Projects, Columbia River Mainstem Facilities, 1984 Final Report.

    SciTech Connect

    Howerton, Jack; Hwang, Diana

    1984-11-01

    This report reviews the status of past, present, and proposed future wildlife planning and mitigation programs at existing hydroelectric projects in the Columbia River Basin. The project evaluations will form the basis for determining any needed remedial measures or additional project analysis. Each hydropower facility report is abstracted separately for inclusion in the Energy Data Base.

  14. How to Select a Project Delivery Method for School Facilities

    ERIC Educational Resources Information Center

    Kalina, David

    2007-01-01

    In this article, the author discusses and explains three project delivery methods that are commonly used today in the United States. The first project delivery method mentioned is the design-bid-build, which is still the predominant method of project delivery for public works and school construction in the United States. The second is the…

  15. Project Title: Nuclear Astrophysics Data from Radioactive Beam Facilities

    SciTech Connect

    Alan A. Chen

    2008-03-27

    The scientific aims of this project have been the evaluation and dissemination of key nuclear reactions in nuclear astrophysics, with a focus on ones to be studied at new radioactive beam facilities worldwide. These aims were maintained during the entire funding period from 2003 - 2006. In the following, a summary of the reactions evaluated during this period is provided. Year 1 (2003-04): {sup 21}Na(p,{gamma}){sup 22}Mg and {sup 18}Ne({alpha},p){sup 21}Na - The importance of the {sup 21}Na(p,{gamma}){sup 22}Mg and the {sup 18}Ne({alpha},p){sup 21}Na reactions in models of exploding stars has been well documented: the first is connected to the production of the radioisotope {sup 22}Na in nova nucleosynthesis, while the second is a key bridge between the Hot-CNO cycles and the rp-process in X-ray bursts. By the end of Summer 2004, our group had updated these reaction rates to include all published data up to September 2004, and cast the reaction rates into standard analytical and tabular formats with the assistance of Oak Ridge National Laboratory's computational infrastructure for reaction rates. Since September 2004, ongoing experiments on these two reactions have been completed, with our group's participation in both: {sup 21}Na(p,{gamma}){sup 22}Mg at the TRIUMF-ISAC laboratory (DRAGON collaboration), and 18Ne({alpha},p){sup 21}Na at Argonne National Laboratory (collaboration with Ernst Rehm, Argonne). The data from the former was subsequently published and included in our evaluation. Publication from the latter still awaits independent confirmation of the experimental results. Year 2 (2004-05): The 25Al(p,{gamma}){sup 26}Si and {sup 13}N(p,{gamma})14O reactions - For Year 2, we worked on evaluations of the {sup 25}Al(p,{gamma}){sup 26}Si and {sup 13}N(p,{gamma}){sup 14}O reactions, in accordance with our proposed deliverables and following similar standard procedures to those used in Year 1. The {sup 25}Al(p,{gamma}){sup 26}Si reaction is a key uncertainty in

  16. Projects at the Component Development and Integration Facility. Quarterly technical progress report, July 1--September 30, 1993

    SciTech Connect

    Not Available

    1993-12-31

    This quarterly technical progress report presents progress on the projects at the Component Development and Integration Facility (CDIF) during the first quarter of FY94. The CDIF is a major US Department of Energy test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: MHD Proof-of-Concept project; mine waste technology pilot program; plasma projects; resource recovery project; sodium sulfide/ferrous sulfate project; soil washing project; and spray casting project.

  17. Projects at the Component Development and Integration Facility. Quarterly technical progress report, October 1--December 31, 1992

    SciTech Connect

    Not Available

    1992-12-31

    This quarterly technical progress report presents progress on the projects at the component Development and Integration Facility (CDIF) during the first quarter of FY93. The CDIF is a major US Department of Energy (DOE) test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: MHD proof-of-concept project; mine waste pilot program; plasma projects; resource recovery project; sodium sulfide/ferrous sulfate project; soil washing project; and spray casting project.

  18. Projects at the Component Development and Integration Facility. Quarterly technical progress report, January 1, 1994--March 31, 1994

    SciTech Connect

    Not Available

    1994-08-01

    This quarterly technical progress report presents progress on the projects at the Component Development and Integration Facility (CDIF) during the second quarter of FY94. The CDIF is a major US Department of Energy test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: Biomass Remediation Project; Heavy Metal-Contaminated Soil Project; MHD Shutdown; Mine Waste Technology Pilot Program; Plasma Projects; Resource Recovery Project; Sodium Sulfide/Ferrous Sulfate Project; and Spray Casting Project.

  19. Projects at the Component Development and Integration Facility. Quarterly technical progress report, April 1--June 30, 1993

    SciTech Connect

    Not Available

    1993-12-01

    This quarterly technical progress report presents progress on the projects at the Component Development and Integration Facility (CDIF) during the third quarter of FY93. The CDIF is a major US Department of Energy test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: MHD Proof-of-Concept Project; Mine Waste Technology Program; Plasma Projects; Resource Recovery Project; Sodium Sulfide/Ferrous Sulfate Project; Soil Washing Project; and Spray Casting Project.

  20. NETL - Fuel Reforming Facilities

    SciTech Connect

    2013-06-12

    Research using NETL's Fuel Reforming Facilities explores catalytic issues inherent in fossil-energy related applications, including catalyst synthesis and characterization, reaction kinetics, catalyst activity and selectivity, catalyst deactivation, and stability.

  1. NETL - Fuel Reforming Facilities

    ScienceCinema

    None

    2014-06-27

    Research using NETL's Fuel Reforming Facilities explores catalytic issues inherent in fossil-energy related applications, including catalyst synthesis and characterization, reaction kinetics, catalyst activity and selectivity, catalyst deactivation, and stability.

  2. Development of Facilities Master Plan and Laboratory Renovation Project

    SciTech Connect

    Fox, Andrea D

    2011-10-03

    Funding from this grant has allowed Morehouse School of Medicine to complete its first professionally developed, comprehensive campus master plan that is in alignment with the recently completed strategic plan. In addition to master planning activities, funds were used for programming and designing research renovations, and also to supplement other research facility upgrades by providing lighting and equipment. The activities funded by this grant will provide the catalyst for substantial improvement in the School's overall facilities for biomedical education and research, and will also provide much of the information needed to conduct a successful campaign to raise funds for proposed buildings and renovations.

  3. Preoperational Environmental Survey for the Spent Nuclear Fuel (SNF) Project Facilities

    SciTech Connect

    MITCHELL, R.M.

    2000-09-28

    This document represents the report for environmental sampling of soil, vegetation, litter, cryptograms, and small mammals at the Spent Nuclear Fuel Project facilities located in 100 K and 200 East Areas in support of the preoperational environmental survey.

  4. Preoperational Environmental Survey for the Spent Nuclear Fuel (SNF) Project Facilities

    SciTech Connect

    MITCHELL, R.M.

    2000-10-12

    This document represents the report for environmental sampling of soil, vegetation, litter, cryptograms, and small mammals at the Spent Nuclear Fuel Project facilities located in 100 K and 200 East Areas in support of the preoperational environmental survey.

  5. Final deactivation report on the Radioisotope Production Lab-E, Building 3032, at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1997-09-01

    The purpose of this report is to document the condition of Bldg. 3032, after completion of deactivation activities as outlined by the Department of Energy (DOE) Office of Nuclear Materials and Facility Stabilization Program (EM-60) guidance documentation. This report outlines the activities conducted to place the facility in a safe and environmentally sound condition for transfer to the DOE Office of Environmental Restoration Program (EM-40). This report provides a history and profile of Bldg. 3032 prior to commencing deactivation activities and a profile of the building after completion of deactivation activities. Turnover items, such as the Postdeactivation Surveillance & Maintenance Plan, remaining hazardous materials, radiological controls, Safeguards and Security, quality assurance, facility operations, and supporting documentation provided in the EM-60 turnover package are discussed. Building 3032 will be used as the Health Physics Office for the Isotopes Facilities Deactivation Program area and will require access for these offices and to facilitate required surveillance and maintenance (S&M) activities to maintain the building safety envelope. Bldg. 3032 was stabilized during deactivation so that when transferred to the EM-40 program, only a minimal S&M effort would be required to maintain the building safety envelope. All materials have been removed from the building, and all utility systems, piping, and alarms have been deactivated except electricity and steam needed for the office areas.

  6. Plasma flux-dependent lipid A deactivation

    NASA Astrophysics Data System (ADS)

    Chang, Hung-Wen; Hsu, Cheng-Che; Ahmed, Musahid; Liu, Suet Yi; Fang, Yigang; Seog, Joonil; Oehrlein, Gottlieb S.; Graves, David B.

    2014-06-01

    This paper reports the influence of gas plasma flux on endotoxin lipid A film deactivation. To study the effect of the flux magnitude of reactive species, a modified low-pressure inductively coupled plasma (ICP) with O radical flux ˜1016 cm-2 s-1 was used. After ICP exposures, it was observed that while the Fourier transform infrared absorbance of fatty chains responsible for the toxicity drops by 80% through the film, no obvious film endotoxin deactivation is seen. This is in contrast to that previously observed under low flux exposure conducted in a vacuum beam system: near-surface only loss of fatty chains led to significant film deactivation. Secondary ion mass spectrometry characterization of changes at the film surface did not appear to correlate with the degree of deactivation. Lipid A films need to be nearly completely removed in order to detect significant deactivation under high flux conditions. Additional high reactive species flux experiments were conducted using an atmospheric pressure helium plasma jet and a UV/ozone device. Exposure of lipid A films to reactive species with these devices showed similar deactivation behaviour. The causes for the difference between low and high flux exposures may be due to the nature of near-surface structural modifications as a function of the rate of film removal.

  7. The Ohio School Facilities Commission. Revamping the State's School Construction Projects.

    ERIC Educational Resources Information Center

    De Patta, Joe

    2001-01-01

    Presents an interview with the Ohio School Facilities Commission's (OSFC) Executive Director who discusses the OSFC's history and its work in managing K-12 school facilities throughout the state. Topics include its efforts to help school districts get bond measures on ballets, funding projects, and its "Partnering Program" for construction…

  8. DEACTIVATION AND DECOMMISSIONING PLANNING AND ANALYSIS WITH GEOGRAPHIC INFORMATION SYSTEMS

    SciTech Connect

    Bollinger, J; William Austin, W; Larry Koffman, L

    2007-09-17

    From the mid-1950's through the 1980's, the U.S. Department of Energy's Savannah River Site produced nuclear materials for the weapons stockpile, for medical and industrial applications, and for space exploration. Although SRS has a continuing defense-related mission, the overall site mission is now oriented toward environmental restoration and management of legacy chemical and nuclear waste. With the change in mission, SRS no longer has a need for much of the infrastructure developed to support the weapons program. This excess infrastructure, which includes over 1000 facilities, will be decommissioned and demolished over the forthcoming years. Dispositioning facilities for decommissioning and deactivation requires significant resources to determine hazards, structure type, and a rough-order-of-magnitude estimate for the decommissioning and demolition cost. Geographic information systems (GIS) technology was used to help manage the process of dispositioning infrastructure and for reporting the future status of impacted facilities.

  9. Project definition study for the National Biomedical Tracer Facility

    SciTech Connect

    Roozen, K.

    1995-02-15

    The University of Alabama at Birmingham (UAB) has conducted a study of the proposed National Biomedical Tracer Facility (NBTF). In collaboration with General Atomics, RUST International, Coleman Research Corporation (CRC), IsoMed, Ernst and Young and the advisory committees, they have examined the issues relevant to the NBTF in terms of facility design, operating philosophy, and a business plan. They have utilized resources within UAB, CRC and Chem-Nuclear to develop recommendations on environmental, safety and health issues. The Institute of Medicine Panel`s Report on Isotopes for Medicine and the Life Sciences took the results of prior workshops further in developing recommendations for the mission of the NBTF. The IOM panel recommends that the NBTF accelerator have the capacity to accelerate protons to 80 MeV and a minimum of 750 microamperes of current. The panel declined to recommend a cyclotron or a linac. They emphasized a clear focus on research and development for isotope production including target design, separation chemistry and generator development. The facility needs to emphasize education and training in its mission. The facility must focus on radionuclide production for the research and clinical communities. The formation of a public-private partnership resembling the TRIUMF-Nordion model was encouraged. An advisory panel should assist with the NBTF operations and prioritization.

  10. Ingham County Medical Care Facility solar energy project (Engineering Materials)

    SciTech Connect

    Not Available

    1983-07-20

    A complete set of as-built drawings for the Ingham County Geriatric Medical Care Facility's solar water heating system is included. These drawings accompany report No. DOE/CS/32382-T1 and DOE/CS/32382-T2. (LS)

  11. Improving the Identification, Dissemination and Implementation of Deactivation and Decommissioning Lessons Learned and Best Practices

    SciTech Connect

    Waisley, Sandra L.; Lackey, Michael B.; Dusek, Lansing G.

    2008-01-15

    Approximately $150 billion of work currently remains in the United States Department of Energy's (DoE's) Office of Environmental Management (EM) life cycle budget for U.S. projects. Contractors who manage facilities for the DOE have been challenged to identify transformational changes to reduce the life cycle costs and to develop a knowledge-management system that identifies, disseminates, and tracks the implementation of lessons learned and best practices. This paper discusses DoE's rationale for using lessons learned and best practices to improve safety and performance while reducing life cycle costs for Deactivation and Decommissioning (D and D) projects. It also provides an update on the Energy Facility Contractors Group's (EFCOG's) progress in supporting DoE's efforts. At this juncture the best practice efforts described are in developmental stages; however, the commitment to and the concrete nature of the work thus far is noteworthy in regard to improving the way D and D lessons learned and best practices are identified, disseminated and implemented across the DOE Complex.

  12. Status and specifications of a Project X front-end accelerator test facility at Fermilab

    SciTech Connect

    Steimel, J.; Webber, R.; Madrak, R.; Wildman, D.; Pasquinelli, R.; Evans-Peoples, E.; /Fermilab

    2011-03-01

    This paper describes the construction and operational status of an accelerator test facility for Project X. The purpose of this facility is for Project X component development activities that benefit from beam tests and any development activities that require 325 MHz or 650 MHz RF power. It presently includes an H- beam line, a 325 MHz superconducting cavity test facility, a 325 MHz (pulsed) RF power source, and a 650 MHz (CW) RF power source. The paper also discusses some specific Project X components that will be tested in the facility. Fermilab's future involves new facilities to advance the intensity frontier. In the early 2000's, the vision was a pulsed, superconducting, 8 GeV linac capable of injecting directly into the Fermilab Main Injector. Prototyping the front-end of such a machine started in 2005 under a program named the High Intensity Neutrino Source (HINS). While the HINS test facility was being constructed, the concept of a new, more versatile accelerator for the intensity frontier, now called Project X, was forming. This accelerator comprises a 3 GeV CW superconducting linac with an associated experimental program, followed by a pulsed 8 GeV superconducting linac to feed the Main Injector synchrotron. The CW Project X design is now the model for Fermilab's future intensity frontier program. Although CW operation is incompatible with the original HINS front-end design, the installation remains useful for development and testing many Project X components.

  13. Beam dynamics simulations and measurements at the Project X Test Facility

    SciTech Connect

    Gianfelice-Wendt, E.; Scarpine, V.E.; Webber, R.C.; /Fermilab

    2011-03-01

    Project X, under study at Fermilab, is a multitask high-power superconducting RF proton beam facility, aiming to provide high intensity protons for rare processes experiments and nuclear physics at low energy, and simultaneously for the production of neutrinos, as well as muon beams in the long term. A beam test facility - former known as High Intensity Neutrino Source (HINS) - is under commissioning for testing critical components of the project, e.g. dynamics and diagnostics at low beam energies, broadband beam chopping, RF power generation and distribution. In this paper we describe the layout of the test facility and present beam dynamics simulations and measurements.

  14. Evaluation of nuclear facility decommissioning projects: summary report. Plum Brook Reactor Facility

    SciTech Connect

    Doerge, D.H.; Miller, R.L.

    1984-02-01

    This document summarizes information concerning the decommissioning of the Plum Brook Reactor Facility, which was placed in a Nuclear Regulatory Commission (NRC) approved safe storage configuration. The data were placed in a computerized information retrieval/manipulation system which permits future utilization of this information in decommissioning of similar facilities. The information is presented both in computer output form and a manually assembled summarization. Complete cost data were not readily available and decommissioning activities did not in all cases conform with current criteria for the SAFSTOR decommissioning mode, therefore no cost comparisons were made.

  15. UO{sub 3} plant turnover - facility description document

    SciTech Connect

    Clapp, D.A.

    1995-01-01

    This document was developed to provide a facility description for those portions of the UO{sub 3} Facility being transferred to Bechtel Hanford Company, Inc. (BHI) following completion of facility deactivation. The facility and deactivated state condition description is intended only to serve as an overview of the plant as it is being transferred to BHI.

  16. Advanced conceptual design report solid waste retrieval facility, phase I, project W-113

    SciTech Connect

    Smith, K.E.

    1994-03-21

    Project W-113 will provide the equipment and facilities necessary to retrieve suspect transuranic (TRU) waste from Trench 04 of the 218W-4C burial ground. As part of the retrieval process, waste drums will be assayed, overpacked, vented, head-gas sampled, and x-rayed prior to shipment to the Phase V storage facility in preparation for receipt at the Waste Receiving and Processing Facility (WRAP). Advanced Conceptual Design (ACD) studies focused on project items warranting further definition prior to Title I design and areas where the potential for cost savings existed. This ACD Report documents the studies performed during FY93 to optimize the equipment and facilities provided in relation to other SWOC facilities and to provide additional design information for Definitive Design.

  17. Tuberculosis infection control in health facilities in Lithuania: lessons learnt from a capacity support project

    PubMed Central

    Ljungqvist, I.; Davidavičiene, E.; Mikaityte, J.; van der Werf, M. J.

    2016-01-01

    Tuberculosis (TB) infection control (IC) is key in controlling TB transmission in health facilities in Lithuania. This article presents a project that aimed at supporting health care facilities in Lithuania in implementing TB-IC. The project consisted of 1) facility TB-IC assessments, 2) development of facility TB-IC plans, 3) TB-IC training and 4) site visits. We assessed the impact of these activities through a self-assessment questionnaire. The project resulted in limited improvements. Most progress was seen in administrative and managerial activities. Possible reasons for the limited improvements are challenges with funding and the lack of supportive legislation and a national TB-IC plan. PMID:27051607

  18. Tuberculosis infection control in health facilities in Lithuania: lessons learnt from a capacity support project.

    PubMed

    Turusbekova, N; Ljungqvist, I; Davidavičiene, E; Mikaityte, J; van der Werf, M J

    2016-03-21

    Tuberculosis (TB) infection control (IC) is key in controlling TB transmission in health facilities in Lithuania. This article presents a project that aimed at supporting health care facilities in Lithuania in implementing TB-IC. The project consisted of 1) facility TB-IC assessments, 2) development of facility TB-IC plans, 3) TB-IC training and 4) site visits. We assessed the impact of these activities through a self-assessment questionnaire. The project resulted in limited improvements. Most progress was seen in administrative and managerial activities. Possible reasons for the limited improvements are challenges with funding and the lack of supportive legislation and a national TB-IC plan. PMID:27051607

  19. Project Management Actions Demolition of a Research Facility Building 431

    SciTech Connect

    Collins, W L

    2005-09-06

    The Demolition of B431 is required to achieve the mission of LLNL and the NNSA FIRP objectives by: (1) Supporting the NNSA Infrastructure Plan goal to ''demolish excess facilities as early as possible''; (2) Banking square footage that allows continued application of advanced science and nuclear technology to the Nation's defense; and (3) Helping maintain and enhance the safety, security, and reliability of the weapons stockpile. A significant effort has been put into the demolition concept in order to ensure that it is well thought out and represents best-value to the government for the money.

  20. FEDERAL FACILITY COMPLIANCE AGREEMENT (FFCA) STACK ISOLATION PROJECT FUNCTIONS & REQUIREMENTS

    SciTech Connect

    TRANBARGER, R.K.

    2003-12-16

    This document delineates the functions and requirements for the FFCA Stack Isolation Project for the 244-A, 244-BX, 244-5, and 244-TX DCRTs. The isolation of each ventilation system and stack includes the electrical, instrumentation, and mechanical isolation of the ventilation system and the installation of primary and annulus breather filters to provide passive ventilation to meet the FFCA requirements.

  1. Project Closeout Report Francium trapping facility at Triumf

    SciTech Connect

    Orozco, Luis A

    2014-09-30

    This is a report of the construction of a Francium Trapping Facility (FTF) at the Isotope Separator and Accelerator (ISAC) of TRIUMF in Vancouver, Canada, where the Francium Parity Non Conservation (FrPNC) international collaboration has its home. This facility will be used to study fundamental symmetries with high-resolution atomic spectroscopy. The primary scientific objective of the program is a measurement of the anapole moment of francium in a chain of isotopes by observing the parity violation induced by the weak interaction. The anapole moment of francium and associated signal are expected to be ten times larger than in cesium, the only element in which an anapole moment has been observed. The measurement will provide crucial information for better understanding weak hadronic interactions in the context of Quantum Chromodynamics (QCD). The methodology combines nuclear and particle physics techniques for the production of francium with precision measurements based on laser cooling and trapping and microwave spectroscopy. The program builds on an initial series of atomic spectroscopy measurements of the nuclear structure of francium, based on isotope shifts and hyperfine anomalies, before conducting the anapole moment measurements, these measurements performed during commissioning runs help understand the atomic and nuclear structure of Fr.

  2. National Ignition Facility Project Completion and Control System Status

    SciTech Connect

    Van Arsdall, P J; Azevedo, S G; Beeler, R G; Bryant, R M; Carey, R W; Demaret, R D; Fisher, J M; Frazier, T M; Lagin, L J; Ludwigsen, A P; Marshall, C D; Mathisen, D G; Reed, R K

    2009-10-02

    The National Ignition Facility (NIF) is the world's largest and most energetic laser experimental system providing a scientific center to study inertial confinement fusion (ICF) and matter at extreme energy densities and pressures. Completed in 2009, NIF is a stadium-sized facility containing a 1.8-MJ, 500-TW 192-beam ultraviolet laser and target chamber. A cryogenic tritium target system and suite of optical, X-ray and nuclear diagnostics will support experiments in a strategy to achieve fusion ignition starting in 2010. Automatic control of NIF is performed by the large-scale Integrated Computer Control System (ICCS), which is implemented by 2 MSLOC of Java and Ada running on 1300 front-end processors and servers. The ICCS framework uses CORBA distribution for interoperation between heterogeneous languages and computers. Laser setup is guided by a physics model and shots are coordinated by data-driven distributed workflow engines. The NIF information system includes operational tools and a peta-scale repository for provisioning experimental results. This paper discusses results achieved and the effort now underway to conduct full-scale operations and prepare for ignition.

  3. The Mixed Waste Management Facility: A DOE technology demonstration project

    SciTech Connect

    Adamson, M.G.; Streit, R.D.

    1994-05-01

    The Mixed Waste Management Facility (MWMF) is a national demonstration test bed that will be used to evaluate, at pilot scale, emerging technologies for the effective treatment of low-level radioactive, organic mixed wastes. The treatment technologies will be selected from candidates of advanced processes that have been sufficiently demonstrated in laboratory and bench-scale tests, and most closely meet suitable criteria for demonstration. The primary and initial goal will be to demonstrate technologies that have the potential to effectively treat a selection of organic-based mixed waste streams, currently in storage within the DOE, that list incineration as the best demonstrated available technology (BDAT). In future operations, the facility may also be used to demonstrate technology that addresses a broader range of government, university, medical, and industry needs. The primary objective of the MWMF is to demonstrate integrated mixed-waste processing technologies. While primary treatment processes are an essential component of integrated treatment trains, they are only a part of a fully integrated demonstration.

  4. Central Japan Synchrotron Radiation Research Facility Project-(II)

    SciTech Connect

    Yamamoto, N.; Takashima, Y.; Hosaka, M.; Takami, K.; Morimoto, H.; Ito, T.; Sakurai, I.; Hara, H.; Okamoto, W.; Watanabe, N.; Takeda, Y.; Katoh, M.; Hori, Y.; Sasaki, S.

    2010-06-23

    A synchrotron radiation facility that is used not only for basic research, but also for engineering and industrial research and development has been proposed to be constructed in the Central area of Japan. The key equipment of this facility is a compact electron storage ring that is able to supply hard X-rays. The circumference of the storage ring is 72 m with the energy of 1.2 GeV, the beam current of 300 mA, and the natural emittance of about 53 nm-rad. The configuration of the storage ring is based on four triple bend cells, and four of the twelve bending magnets are 5 T superconducting ones. The bending angle and critical energy are 12 degree and 4.8 keV, respectively. For the top-up operation, the electron beam will be injected from a booster synchrotron with the full energy. Currently, six beamlines are planned for the first phase starting from 2012.

  5. Mixed and low-level waste treatment facility project

    SciTech Connect

    Not Available

    1992-04-01

    The technology information provided in this report is only the first step toward the identification and selection of process systems that may be recommended for a proposed mixed and low-level waste treatment facility. More specific information on each technology will be required to conduct the system and equipment tradeoff studies that will follow these preengineering studies. For example, capacity, maintainability, reliability, cost, applicability to specific waste streams, and technology availability must be further defined. This report does not currently contain all needed information; however, all major technologies considered to be potentially applicable to the treatment of mixed and low-level waste are identified and described herein. Future reports will seek to improve the depth of information on technologies.

  6. Optical assembly and alignment for the National Ignition Facility project

    SciTech Connect

    Hurst, P.A.; Grasz, E.L.; Wong, H.; Schmitt, E.H.; Simmons, M.R.

    1997-12-23

    The National Ignition Facility (NIF) will use about 8,000 large optics to carry a high-power laser through a stadium-size building, and will do so on a very tight schedule and budget. The collocated Optics Assembly Building (OAB) will assemble and align, in a clean-room environment, the NIF`s large optics, which are the biggest optics ever assembled in such an environment. In addition, the OAB must allow for just-in-time processing and clean transfer to the areas where the optics will be used. By using a mixture of off-the-shelf and newly designed equipment and by working with industry, we have developed innovative handling systems to perform the clean assembly and precise alignment required for the full variety of optics, as well as for postassembly inspection. We have also developed a set of loading mechanisms that safely get the clean optics to their places in the main NIF building.

  7. Initial deactivation of residue hydrometallation catalysts

    SciTech Connect

    Gualda, G.; Kasztelan, S.

    1995-12-31

    A strong deactivation of residue hydrodemetallization catalysts is usually observed in the first days of a run. We report in this work a comparative study of the deactivation of a NiMo/alumina catalyst with a special pore structure so-called {open_quotes}chestnut burr{close_quotes} by coke and metal+coke deposits. The former set of samples were prepared in batch reactor by varying operating conditions and the latter set of samples were prepared in continuous flow reactor in both cases using a Safaniya atmospheric residue. Various methods were employed to characterize the deposits (TEM, XPS, EPMA, Surface area measurements, porosimetry, etc...) including catalytic tests of the used catalyst with various model reactants, it has been found that metal deposits are responsible for the initial deactivation of the residue hydrodametallation catalyst used in this work.

  8. Novel Muon Beam Facilities for Project X at Fermilab

    SciTech Connect

    Neuffer, D.V.; Ankenbrandt, C.M.; Abrams, R.; Roberts, T.J.; Yoshikawa, C.Y.; /MUONS Inc., Batavia

    2012-05-01

    Innovative muon beam concepts for intensity-frontier experiments such as muon-to-electron conversion are described. Elaborating upon a previous single-beam idea, we have developed a design concept for a system to generate four high quality, low-energy muon beams (two of each sign) from a single beam of protons. As a first step, the production of pions by 1 and 3 GeV protons from the proposed Project X linac at Fermilab is being simulated and compared with the 8-GeV results from the previous study.

  9. Multi-Function Waste Tank Facility Quality Assurance Program Plan, Project W-236A. Revision 2

    SciTech Connect

    Hall, L.R.

    1995-05-30

    This document describes the Quality Assurance (QA) program for the Multi-Function Waste Tank Facility (MWTF) Project. The purpose of this QA program is to control project activities in such a manner as to achieve the mission of the MWTF Project in a safe and reliable manner. The QA program for the MWTF Project is founded on DOE Order 5700.6C, Quality Assurance, and implemented through the use of ASME NQA-1, Quality Assurance Program Requirements for Nuclear Facilities (ASME 1989 with addenda la-1989, lb-1991 and lc-1992). This document describes the program and planned actions which the Westinghouse Hanford Company (WHC) will implement to demonstrate and ensure that the project meets the requirements of DOE Order 5700.6C through the interpretive guidance of ASME NQA-1.

  10. Human factors engineering for the TERF (Tritium Emissions Reduction Facility) project. [Tritium Emissions Reduction Facility

    SciTech Connect

    Hedley, W.H.; Adams, F.S. ); Wells, J.E. )

    1990-12-14

    The Tritium Emissions Reduction Facility (TERF) is being built by EG G Mound Applied Technologies to provide improved control of the tritium emissions from gas streams being processed. Mound handles tritium in connection with production, development, research, disassembly, recovery, and surveillance operations. During these operations, a small fraction of the tritium being processed escapes from its original containment. The objective of this report is to describe the human factors engineering as performed in connection with the design, construction, and testing of the TERF as required in DOE Order 6430.1A, section 1300-12. Human factors engineering has been involved at each step of the process and was considered during the preliminary research on tritium capture before selecting the specific process to be used. Human factors engineering was also considered in determining the requirements for the TERF and when the specific design work was initiated on the facility and the process equipment. Finally, human factors engineering was used to plan the specific acceptance tests that will be made during TERF installation and after its completion. These tests will verify the acceptability of the final system and its components. 16 refs., 8 figs.

  11. Manhattan Project buildings and facilities at the Hanford Site: A construction history

    SciTech Connect

    Gerber, M.S.

    1993-09-01

    This document thoroughly examines the role that the Hanford Engineer Works played in the Manhattan project. The historical aspects of the buildings and facilities are characterized. An in depth look at the facilities, including their functions, methods of fabrication and appearance is given for the 100 AREAS, 200 AREAS, 300 AREAS, 500, 800 and 900 AREAS, 600 AREA, 700 AREA, 1100 AREA and temporary construction structures.

  12. SEISMIC DESIGN REQUIREMENTS SELECTION METHODOLOGY FOR THE SLUDGE TREATMENT & M-91 SOLID WASTE PROCESSING FACILITIES PROJECTS

    SciTech Connect

    RYAN GW

    2008-04-25

    In complying with direction from the U.S. Department of Energy (DOE), Richland Operations Office (RL) (07-KBC-0055, 'Direction Associated with Implementation of DOE-STD-1189 for the Sludge Treatment Project,' and 08-SED-0063, 'RL Action on the Safety Design Strategy (SDS) for Obtaining Additional Solid Waste Processing Capabilities (M-91 Project) and Use of Draft DOE-STD-I 189-YR'), it has been determined that the seismic design requirements currently in the Project Hanford Management Contract (PHMC) will be modified by DOE-STD-1189, Integration of Safety into the Design Process (March 2007 draft), for these two key PHMC projects. Seismic design requirements for other PHMC facilities and projects will remain unchanged. Considering the current early Critical Decision (CD) phases of both the Sludge Treatment Project (STP) and the Solid Waste Processing Facilities (M-91) Project and a strong intent to avoid potentially costly re-work of both engineering and nuclear safety analyses, this document describes how Fluor Hanford, Inc. (FH) will maintain compliance with the PHMC by considering both the current seismic standards referenced by DOE 0 420.1 B, Facility Safety, and draft DOE-STD-1189 (i.e., ASCE/SEI 43-05, Seismic Design Criteria for Structures, Systems, and Components in Nuclear Facilities, and ANSI!ANS 2.26-2004, Categorization of Nuclear Facility Structures, Systems and Components for Seismic Design, as modified by draft DOE-STD-1189) to choose the criteria that will result in the most conservative seismic design categorization and engineering design. Following the process described in this document will result in a conservative seismic design categorization and design products. This approach is expected to resolve discrepancies between the existing and new requirements and reduce the risk that project designs and analyses will require revision when the draft DOE-STD-1189 is finalized.

  13. 7 CFR Appendix D to Subpart E of... - Alcohol Production Facilities Planning, Performing, Development and Project Control

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ..., Development and Project Control D Appendix D to Subpart E of Part 1980 Agriculture Regulations of the... of Part 1980—Alcohol Production Facilities Planning, Performing, Development and Project Control (I) Design Policy. The borrower shall ensure or cause to be ensured that: (A) All project facilities...

  14. Project Hanford management contract quality assurance program implementation plan for nuclear facilities

    SciTech Connect

    Bibb, E.K.

    1997-10-15

    During transition from the Westinghouse Hanford Company (WHC) Management and Operations (M and O) contract to the Fluor Daniel Hanford (FDH) Management and Integration (M and I) contract, existing WHC policies, procedures, and manuals were reviewed to determine which to adopt on an interim basis. Both WHC-SP-1131,Hanford Quality Assurance Program and Implementation Plan, and WHC-CM-4-2, Quality Assurance Manual, were adopted; however, it was recognized that revisions were required to address the functions and responsibilities of the Project Hanford Management Contract (PHMC). This Quality Assurance Program Implementation Plan for Nuclear Facilities (HNF-SP-1228) supersedes the implementation portion of WHC-SP-1 13 1, Rev. 1. The revised Quality Assurance (QA) Program is documented in the Project Hanford Quality Assurance Program Description (QAPD), HNF-MP-599. That document replaces the QA Program in WHC-SP-1131, Rev. 1. The scope of this document is limited to documenting the nuclear facilities managed by FDH and its Major Subcontractors (MSCS) and the status of the implementation of 10 CFR 830.120, Quality Assurance Requirements, at those facilities. Since the QA Program for the nuclear facilities is now documented in the QAPD, future updates of the information provided in this plan will be by letter. The layout of this plan is similar to that of WHC-SP-1 13 1, Rev. 1. Sections 2.0 and 3.0 provide an overview of the Project Hanford QA Program. A list of Project Hanford nuclear facilities is provided in Section 4.0. Section 5.0 provides the status of facility compliance to 10 CFR 830.120. Sections 6.0, 7.0, and 8.0 provide requested exemptions, status of open items, and references, respectively. The four appendices correspond to the four projects that comprise Project Hanford.

  15. Quality assurance project plan for the UMTRA technical assistance contractor hydrochemistry facility. Final report

    SciTech Connect

    1993-07-01

    The Uranium Mill Tailings Remedial Action (UMTRA) hydrochemistry facility is used to perform a limited but important set of services for the UMTRA Project. Routine services include support of field-based hydrological and geochemical operations and water sampling activities. Less commonly, the hydrology and geochemistry staff undertake special studies and site characterization studies at this facility. It is also used to train hydrologists, geochemists, and groundwater sampling crews. A review of this Quality Assurance Project Plan (QAPP) shall be accomplished once each calendar year. This review will be targeted to be accomplished not sooner than 6 months and not later than 18 months after the last review.

  16. Mechanotransduction in neutrophil activation and deactivation.

    PubMed

    Ekpenyong, Andrew E; Toepfner, Nicole; Chilvers, Edwin R; Guck, Jochen

    2015-11-01

    Mechanotransduction refers to the processes through which cells sense mechanical stimuli by converting them to biochemical signals and, thus, eliciting specific cellular responses. Cells sense mechanical stimuli from their 3D environment, including the extracellular matrix, neighboring cells and other mechanical forces. Incidentally, the emerging concept of mechanical homeostasis,long term or chronic regulation of mechanical properties, seems to apply to neutrophils in a peculiar manner, owing to neutrophils' ability to dynamically switch between the activated/primed and deactivated/deprimed states. While neutrophil activation has been known for over a century, its deactivation is a relatively recent discovery. Even more intriguing is the reversibility of neutrophil activation and deactivation. We review and critically evaluate recent findings that suggest physiological roles for neutrophil activation and deactivation and discuss possible mechanisms by which mechanical stimuli can drive the oscillation of neutrophils between the activated and resting states. We highlight several molecules that have been identified in neutrophil mechanotransduction, including cell adhesion and transmembrane receptors, cytoskeletal and ion channel molecules. The physiological and pathophysiological implications of such mechanically induced signal transduction in neutrophils are highlighted as a basis for future work. This article is part of a Special Issue entitled: Mechanobiology. PMID:26211453

  17. Deactivation efficiency of stabilized bactericidal emulsions.

    PubMed

    Vyhnalkova, Renata; Eisenberg, Adi; van de Ven, Theo G M

    2011-09-20

    Biocide emulsions stabilized with various stabilizing agents were prepared and characterized, and their efficiency in bacteria deactivation was evaluated. A number of stabilizing agents were tested for their stabilizing effect on emulsions of thiocyanomethylthiobenzothiazole (TCMTB) biocide. Two agents, the most successful in stabilizing the biocide, were chosen for further studies: high molecular weight polyethyleneimine (PEI) and an amphiphilic block copolymer of poly(caprolactone)-b-poly(acrylic acid) (PCL(33)-b-PAA(33)). The emulsion droplet sizes varied between 325 and 500 nm. Deactivation of bacteria was studied by exposing E. coli ATCC 11229 bacteria dispersions to emulsions stabilized by positively charged PEI or negatively charged PCL-b-PAA micelles and by measuring their absorbance; E. coli do not grow with time in the presence of biocide emulsions. PEI molecules alone act as biocide and deactivate the bacteria. PCL-b-PAA micelles as stabilizing agent do not affect the growth of the E. coli ; bacteria are deactivated by TCMTB released from the emulsion droplets. The kinetics of emulsion dissolution studies revealed for both stabilizing agents a decrease in droplet size with time while the emulsions were subjected to dialysis. The biocide was released from the emulsions within ∼250 min; the droplet shells consist mostly of PEI or PCL-b-PAA insoluble complexes with the biocide, which do not dissolve during dialysis. SEM images confirm the presence of residual crumbled shells with holes after 24 h of dialysis. PMID:21823610

  18. The Approach of Emotional Deactivation of Prejudice

    ERIC Educational Resources Information Center

    Boucher, Jean-Nil

    2011-01-01

    The aim of the approach of emotional deactivation is to help students reduce the prejudice they may feel towards diverse social groups. Be those groups homosexuals, people living with a disability or immigrants, the victims of prejudice are invited to come into classrooms and to confront the preconceptions that students have in their respect.…

  19. Sharing lessons learned and best practices in deactivation and decommissioning techniques among U.S. Department of Energy contractors

    SciTech Connect

    Lackey, Michael B.; Waisley, Sandra L.; Dusek, Lansing G.

    2007-07-01

    Approximately $153.2 billion of work currently remains in the United States Department of Energy's (DOE's) Office of Environmental Management (EM) life cycle budget for United States projects. Contractors who manage facilities for the DOE have been challenged to identify transformational changes to reduce the life cycle costs and develop a knowledge management system that identifies, disseminates, and tracks the implementation of lessons learned and best practices. At the request of the DOE's EM Office of Engineering and Technology, the Energy Facility Contractors Group (EFCOG) responded to the challenge with formation of the Deactivation and Decommissioning (D and D) and Facility Engineering (DD/FE) Working Group. Since October 2006, members have already made significant progress in realizing their goals: adding new D and D best practices to the existing EFCOG Best Practices database; participating in lessons learned forums; and contributing to a DOE initiative on identifying technology needs. The group is also participating in a DOE project management initiative to develop implementation guidelines, as well as a DOE radiation protection initiative to institute a more predictable and standardized approach to approving authorized limits and independently verifying cleanup completion at EM sites. Finally, a D and D hotline to provide real-time solutions to D and D challenges is also being launched. (authors)

  20. Projects at the Component Development and Integration Facility. Quarterly technical progress report, January 1--March 31, 1993

    SciTech Connect

    Not Available

    1993-09-01

    This quarterly technical progress report presents progress on several different projects at the Component Development and Integration Facility (CDIF) during the second quarter of FY93. The CDIF is a major US Department of Energy test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: MHD Proof-of-Concept Project; Mine Waste Technology Pilot Program; Plasma Furnace Projects for waste destruction; Resource Recovery Project; Sodium Sulfide/Ferrous Sulfate Project; Soil Washing Project for removal of radioactive materials; and Spray Casting Project.

  1. Application of scene projection technologies at the AMRDEC SSDD HWIL facilities

    NASA Astrophysics Data System (ADS)

    Gareri, Jeffrey P.; Ballard, Gary H.; Morris, Joseph W.; Bunfield, Dennis; Saylor, Danny

    2012-06-01

    State-of-the-art hardware-in-the-loop (HWIL) test facilities have been established and in operation at the U.S. Army's Aviation and Missile Research, Development, and Engineering Center (AMRDEC) in McMorrow Laboratories, on Redstone Arsenal Alabama for over 37 years. These facilities have been successfully developed and employed supporting numerous tactical and interceptor missile systems. The AMRDEC HWIL facilities are constantly in a state state of modification and revision supporting evolving test requirements related to increasingly complex sensor suites, guidance implementations, and employment strategies prevalent within both existing and emerging aviation and missile programs. . This paper surveys the role of the U.S. Army Aviation and Missile Research, Development, and Engineering Center (AMRDEC) in the development and operation of HWIL test facilities and the implementation of new, innovative technologies that have been integrated within facility test assets. This technology spans both the Near IR (NIR- 1.064um) and IR (3 - 12um) and RF (2 - 95 GHz) operating ranges. The AMRDEC HWIL facilities represent the highest degree of simulation fidelity, integrating all the major parts of a HWIL simulation including tactical missile and seeker hardware, executive control software, scene generation, and NIR, IR or RF scene projection systems. Successful incorporation of scene generation and projection technologies have become a key thrust of the AMRDEC HWIL development focus, with the intention to adapt and anticipate emerging test element requirements necessitated by future system sensing technologies.

  2. Design review plan for Multi-Function Waste Tank Facility (Project W-236A)

    SciTech Connect

    Renfro, G.G.

    1994-12-20

    This plan describes how the Multi-Function Waste Tank Facility (MWTF) Project conducts reviews of design media; describes actions required by Project participants; and provides the methodology to ensure that the design is complete, meets the technical baseline of the Project, is operable and maintainable, and is constructable. Project W-236A is an integrated project wherein the relationship between the operating contractor and architect-engineer is somewhat different than that of a conventional project. Working together, Westinghouse Hanford Company (WHC) and ICF Karser Hanford (ICF KH) have developed a relationship whereby ICF KH performs extensive design reviews and design verification. WHC actively participates in over-the-shoulder reviews during design development, performs a final review of the completed design, and conducts a formal design review of the Safety Class I, ASME boiler and Pressure Vessel Code items in accordance with WHC-CM-6-1, Standard Engineering Practices.

  3. 50 CFR 80.64 - How does an agency allocate costs in multipurpose projects and facilities?

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... RESTORATION PROGRAM ADMINISTRATIVE REQUIREMENTS, PITTMAN-ROBERTSON WILDLIFE RESTORATION AND DINGELL-JOHNSON SPORT FISH RESTORATION ACTS Allocation of Funds by an Agency § 80.64 How does an agency allocate costs... project or facility. The agency must describe the method used to allocate costs in multipurpose...

  4. 50 CFR 80.64 - How does an agency allocate costs in multipurpose projects and facilities?

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... RESTORATION PROGRAM ADMINISTRATIVE REQUIREMENTS, PITTMAN-ROBERTSON WILDLIFE RESTORATION AND DINGELL-JOHNSON SPORT FISH RESTORATION ACTS Allocation of Funds by an Agency § 80.64 How does an agency allocate costs... project or facility. The agency must describe the method used to allocate costs in multipurpose...

  5. 50 CFR 80.64 - How does an agency allocate costs in multipurpose projects and facilities?

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... RESTORATION PROGRAM ADMINISTRATIVE REQUIREMENTS, PITTMAN-ROBERTSON WILDLIFE RESTORATION AND DINGELL-JOHNSON SPORT FISH RESTORATION ACTS Allocation of Funds by an Agency § 80.64 How does an agency allocate costs... project or facility. The agency must describe the method used to allocate costs in multipurpose...

  6. 50 CFR 80.64 - How does an agency allocate costs in multipurpose projects and facilities?

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... RESTORATION PROGRAM ADMINISTRATIVE REQUIREMENTS, PITTMAN-ROBERTSON WILDLIFE RESTORATION AND DINGELL-JOHNSON SPORT FISH RESTORATION ACTS Allocation of Funds by an Agency § 80.64 How does an agency allocate costs... project or facility. The agency must describe the method used to allocate costs in multipurpose...

  7. Information Retrieval in an Office Filing Facility and Future Work in Project Minstrel.

    ERIC Educational Resources Information Center

    Smeaton, A. F.; van Rijsbergen, C. J.

    1986-01-01

    Review of office filing facility filing and retrieval mechanisms for unstructured and mixed media information focuses on free text methods. Also discussed are the state of the art in handling voice and image data, problems with searching text surrogates to implement free text content retrieval, and work of Project Minstrel. (Author/MBR)

  8. Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

    SciTech Connect

    Pickett, W.W.

    1997-12-30

    This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations.

  9. Evolution of Safeguards over Time: Past, Present, and Projected Facilities, Material, and Budget

    SciTech Connect

    Kollar, Lenka; Mathews, Caroline E.

    2009-07-01

    This study examines the past trends and evolution of safeguards over time and projects growth through 2030. The report documents the amount of nuclear material and facilities under safeguards from 1970 until present, along with the corresponding budget. Estimates for the future amount of facilities and material under safeguards are made according to non-nuclear-weapons states’ (NNWS) plans to build more nuclear capacity and sustain current nuclear infrastructure. Since nuclear energy is seen as a clean and economic option for base load electric power, many countries are seeking to either expand their current nuclear infrastructure, or introduce nuclear power. In order to feed new nuclear power plants and sustain existing ones, more nuclear facilities will need to be built, and thus more nuclear material will be introduced into the safeguards system. The projections in this study conclude that a zero real growth scenario for the IAEA safeguards budget will result in large resource gaps in the near future.

  10. Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

    SciTech Connect

    IRWIN, J.J.

    2000-02-03

    This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

  11. Benchmarking the Remote-Handled Waste Facility at the West Valley Demonstration Project

    SciTech Connect

    O. P. Mendiratta; D. K. Ploetz

    2000-02-29

    ABSTRACT Facility decontamination activities at the West Valley Demonstration Project (WVDP), the site of a former commercial nuclear spent fuel reprocessing facility near Buffalo, New York, have resulted in the removal of radioactive waste. Due to high dose and/or high contamination levels of this waste, it needs to be handled remotely for processing and repackaging into transport/disposal-ready containers. An initial conceptual design for a Remote-Handled Waste Facility (RHWF), completed in June 1998, was estimated to cost $55 million and take 11 years to process the waste. Benchmarking the RHWF with other facilities around the world, completed in November 1998, identified unique facility design features and innovative waste pro-cessing methods. Incorporation of the benchmarking effort has led to a smaller yet fully functional, $31 million facility. To distinguish it from the June 1998 version, the revised design is called the Rescoped Remote-Handled Waste Facility (RRHWF) in this topical report. The conceptual design for the RRHWF was completed in June 1999. A design-build contract was approved by the Department of Energy in September 1999.

  12. Integrated Framework for Patient Safety and Energy Efficiency in Healthcare Facilities Retrofit Projects.

    PubMed

    Mohammadpour, Atefeh; Anumba, Chimay J; Messner, John I

    2016-07-01

    There is a growing focus on enhancing energy efficiency in healthcare facilities, many of which are decades old. Since replacement of all aging healthcare facilities is not economically feasible, the retrofitting of these facilities is an appropriate path, which also provides an opportunity to incorporate energy efficiency measures. In undertaking energy efficiency retrofits, it is vital that the safety of the patients in these facilities is maintained or enhanced. However, the interactions between patient safety and energy efficiency have not been adequately addressed to realize the full benefits of retrofitting healthcare facilities. To address this, an innovative integrated framework, the Patient Safety and Energy Efficiency (PATSiE) framework, was developed to simultaneously enhance patient safety and energy efficiency. The framework includes a step -: by -: step procedure for enhancing both patient safety and energy efficiency. It provides a structured overview of the different stages involved in retrofitting healthcare facilities and improves understanding of the intricacies associated with integrating patient safety improvements with energy efficiency enhancements. Evaluation of the PATSiE framework was conducted through focus groups with the key stakeholders in two case study healthcare facilities. The feedback from these stakeholders was generally positive, as they considered the framework useful and applicable to retrofit projects in the healthcare industry. PMID:27492415

  13. Environmental assessment for the Waste Water Treatment Facility at the West Valley Demonstration Project and finding of no significant impact

    SciTech Connect

    Not Available

    1992-12-31

    The possible environmental impacts from the construction and operation of a waste water treatment facility for the West Valley Demonstration Project are presented. The West Valley Project is a demonstration project on the solidification of high-level radioactive wastes. The need for the facility is the result of a rise in the work force needed for the project which rendered the existing sewage treatment plant incapable of meeting the nonradioactive waste water treatment needs.

  14. Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management

    SciTech Connect

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system.

  15. As Built Verification Plan for Cask Transportation Facility Modifications (CTFM) Project A.5 and A.6

    SciTech Connect

    LANE, K.I.

    2000-04-20

    This document establishes an As-built Verification Plan (AVP) for implementing requirements in PHMC Engineering Requirements HNF-PRO-1819, Rev. 4, Sections 2.8.3.d and 2.10.8 and Spent Nuclear Fuels (SNF) Project Administrative Procedure EN-6-012-01. This AVP defines and implements approved processes to document the physical configuration of the project scope installed within the facility and identify discrepancies between the associated project engineering drawings and the field configuration, and the component index (CI) database as defined in AP EN 6-005-02. This AVP defines requirements for project activities verifying conformance of structures, systems, and components (SSCs) to project specified requirements.

  16. Overview of progress on the improvement projects for the LANSCE accelerator and target facilities

    SciTech Connect

    Macek, R.J.; Browne, J.; Brun, T.; Donahue, J.B.; Fitzgerald, D.H.; Hoffman, E.; Pynn, R.; Schriber, S.; Weinacht, D.

    1997-06-01

    Three projects have been initiated since 1994 to improve the performance of the accelerator and target facilities for the Los Alamos Neutron Science Center (LANSCE). The LANSCE Reliability Improvement Project (LRIP) was separated into two phases. Phase 1, completed in 1995, targeted near-term improvements to beam reliability and availability that could be completed in one-year`s time. Phase 2, now underway and scheduled for completion in May 1998, consists of two projects: (a) implementation of direct H-injection for the Proton Storage Ring (PSR) and (b) an upgrade of the target/moderator system for the short pulse spallation neutron (SPSS) source. The latter will reduce the target change-out time from about 10 months to about three weeks. The third project, the SPSS Enhancement Project, is aimed at increasing the PSR output beam current to 200 {micro}A at 30 Hz and providing up to seven new neutron scattering instruments.

  17. Highlights of the ISOLDE facility and the HIE-ISOLDE project

    NASA Astrophysics Data System (ADS)

    Borge, M. J. G.

    2016-06-01

    The ISOLDE facility is an ISOL-based radioactive beam facility at CERN. It is dedicated to the production and research of nuclei far from stability. Exotic nuclei of variety of chemical elements are available for the study of nuclear structure, nuclear astrophysics, fundamental symmetries and atomic physics, as well as for applications in condensed-matter and life sciences. Since longer than a decade it has offered the largest variety of post-accelerated radioactive beams in the world. In order to broaden the scientific opportunities beyond the present ISOLDE facility, the on-going HIE-ISOLDE (High Intensity and Energy) project will provide major improvements in energy range, beam intensity and beam quality. The first phase will boost the beam energy of the current REX LINAC to 5.5 MeV/u resulting in larger cross sections for Coulomb excitation compared to the previous maximum energy of 3 MeV/u. Higher energies will also open up many transfer reaction channels. Physics with post-accelerated beams starts in autumn 2015. The second phase of the project is already approved and is expected to be completed in 2018 allowing beam energies up to 10 MeV/u for A/q = 4.5. In this contribution the present status of the ISOLDE facility including some highlights will be discussed. The HIE-ISOLDE project will be described together with a panorama of the physics cases to be addressed.

  18. Temperature (de)activated patchy colloidal particles

    NASA Astrophysics Data System (ADS)

    de las Heras, Daniel; Telo da Gama, Margarida M.

    2016-06-01

    We present a new model of patchy particles in which the interaction sites can be activated or deactivated by varying the temperature of the system. We study the thermodynamics of the system by means of Wertheim’s first order perturbation theory, and use Flory–Stockmayer theory of polymerization to analyse the percolation threshold. We find a very rich phase behaviour including lower critical points and reentrant percolation.

  19. Temperature (de)activated patchy colloidal particles.

    PubMed

    de Las Heras, Daniel; da Gama, Margarida M Telo

    2016-06-22

    We present a new model of patchy particles in which the interaction sites can be activated or deactivated by varying the temperature of the system. We study the thermodynamics of the system by means of Wertheim's first order perturbation theory, and use Flory-Stockmayer theory of polymerization to analyse the percolation threshold. We find a very rich phase behaviour including lower critical points and reentrant percolation. PMID:27115118

  20. 50 CFR 80.63 - Does an agency have to allocate costs in multipurpose projects and facilities?

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... RESTORATION PROGRAM ADMINISTRATIVE REQUIREMENTS, PITTMAN-ROBERTSON WILDLIFE RESTORATION AND DINGELL-JOHNSON SPORT FISH RESTORATION ACTS Allocation of Funds by an Agency § 80.63 Does an agency have to allocate... in multipurpose projects and facilities. A grant-funded project or facility is multipurpose if...

  1. 50 CFR 80.63 - Does an agency have to allocate costs in multipurpose projects and facilities?

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... RESTORATION PROGRAM ADMINISTRATIVE REQUIREMENTS, PITTMAN-ROBERTSON WILDLIFE RESTORATION AND DINGELL-JOHNSON SPORT FISH RESTORATION ACTS Allocation of Funds by an Agency § 80.63 Does an agency have to allocate... in multipurpose projects and facilities. A grant-funded project or facility is multipurpose if...

  2. 50 CFR 80.63 - Does an agency have to allocate costs in multipurpose projects and facilities?

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... RESTORATION PROGRAM ADMINISTRATIVE REQUIREMENTS, PITTMAN-ROBERTSON WILDLIFE RESTORATION AND DINGELL-JOHNSON SPORT FISH RESTORATION ACTS Allocation of Funds by an Agency § 80.63 Does an agency have to allocate... in multipurpose projects and facilities. A grant-funded project or facility is multipurpose if...

  3. 50 CFR 80.63 - Does an agency have to allocate costs in multipurpose projects and facilities?

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... RESTORATION PROGRAM ADMINISTRATIVE REQUIREMENTS, PITTMAN-ROBERTSON WILDLIFE RESTORATION AND DINGELL-JOHNSON SPORT FISH RESTORATION ACTS Allocation of Funds by an Agency § 80.63 Does an agency have to allocate... in multipurpose projects and facilities. A grant-funded project or facility is multipurpose if...

  4. RCRA (Resource Conservation and Recovery Act) ground-water monitoring projects for Hanford facilities: Annual Progress Report for 1989

    SciTech Connect

    Smith, R.M.; Gorst, W.R.

    1990-03-01

    This report describes the progress during 1989 of 16 Hanford Site ground-water monitoring projects covering 25 hazardous waste facilities and 1 nonhazardous waste facility. Each of the projects is being conducted according to federal regulations based on the Resource Conservation and Recovery Act of 1976 and the State of Washington Administrative Code. 40 refs., 75 figs., 6 tabs.

  5. Photophysical deactivation pathways in adenine oligonucleotides.

    PubMed

    Spata, Vincent A; Matsika, Spiridoula

    2015-12-14

    In this work we study deactivation processes in adenine oligomers after absorption of UV radiation using Quantum Mechanics combined with Molecular Mechanics (QM/MM). Correlated electronic structure methods appropriate for describing the excited states are used to describe a π-stacked dimer of adenine bases incorporated into (dA)20(dT)20. The results of these calculations reveal three different types of excited state minima which play a role in deactivation processes. Within this set of minima there are minima where the excited state is localized on one adenine (monomer-like) as well as minima where the excited state is delocalized on two adenines, forming different types of excimers and bonded excimers of varying but inter-related character. The proximity of their energies reveals that the minima can decay into one another along a flat potential energy surface dependent on the interbase separation. Additionally, analysis of the emissive energies and other physical properties, including theoretical anisotropy calculations, and comparison with fluorescence experiments, provides evidence that excimers play an important role in long-lived signals in adenine oligonucleotides while the subpicosecond decay is attributed to monomer-like minima. The necessity for a close approach of the nucleobases reveals that the deactivation mechanism is tied to macro-molecular motion. PMID:26536353

  6. Lead Paint Analyzer. Deactivation and Decommissioning Focus Area. OST Reference #2317

    SciTech Connect

    None, None

    1999-09-01

    The U.S. Department of Energy (DOE) continually seeks safer and more cost-effective technologies for use in decontamination and decommissioning (D&D) of nuclear facilities. To this end, the Deactivation and Decommissioning Focus Area (DDFA) of the DOE’s Office of Science and Technology (OST) sponsors Large-Scale Demonstration and Deployment Projects (LSDDP). At these LSDDPs, developers and vendors of improved or innovative technologies showcase products that are potentially beneficial to DOE’s projects, and to others in the D&D community. Benefits sought include decreased health and safety risks to personnel and the environment, increased productivity, and decreased cost of operation. The Idaho National Engineering and Environmental Laboratory (INEEL) LSDDP generated a list of statements defining specific needs or problems where improved technology could be incorporated into ongoing D&D tasks. One of the stated needs was for a Lead Paint Analyzer that would reduce costs and shorten schedules in DOE’s Decommissioning Project. The Niton 700 Series Multi-element Analyzer is a hand-held, battery-operated unit that uses x-ray fluorescence spectroscopy (XRF) to analyze 25 elements, including the presence of lead in paint. The baseline technologies consist of collecting field samples and sending the samples to a laboratory for analysis. This demonstration investigated the associated costs and the required time to take an analysis with the multi-element analyzer with respect to the baseline technology. The Niton 700 Series Multi-element Analyzer performs in situ real-time analyses to identify and quantify lead, chromium, cadmium, and other metals in lead-based paint. Benefits expected from using the multi-element spectrum analyzer include: Reduced cost; Easier use; Reduced schedules in DOE’s decommissioning projects.

  7. Space Station Furnace Facility Preliminary Project Implementation Plan (PIP). Volume 2, Appendix 2

    NASA Technical Reports Server (NTRS)

    Perkey, John K.

    1992-01-01

    The Space Station Furnace Facility (SSFF) is an advanced facility for materials research in the microgravity environment of the Space Station Freedom and will consist of Core equipment and various sets of Furnace Module (FM) equipment in a three-rack configuration. This Project Implementation Plan (PIP) document was developed to satisfy the requirements of Data Requirement Number 4 for the SSFF study (Phase B). This PIP shall address the planning of the activities required to perform the detailed design and development of the SSFF for the Phase C/D portion of this contract.

  8. Project C-018H, 242-A Evaporator/PUREX Plant Process Condensate Treatment Facility, functional design criteria. Revision 3

    SciTech Connect

    Sullivan, N.

    1995-05-02

    This document provides the Functional Design Criteria (FDC) for Project C-018H, the 242-A Evaporator and Plutonium-Uranium Extraction (PUREX) Plant Condensate Treatment Facility (Also referred to as the 200 Area Effluent Treatment Facility [ETF]). The project will provide the facilities to treat and dispose of the 242-A Evaporator process condensate (PC), the Plutonium-Uranium Extraction (PUREX) Plant process condensate (PDD), and the PUREX Plant ammonia scrubber distillate (ASD).

  9. Conceptual Design Report: Nevada Test Site Mixed Waste Disposal Facility Project

    SciTech Connect

    NSTec Environmental Management

    2009-01-31

    Environmental cleanup of contaminated nuclear weapons manufacturing and test sites generates radioactive waste that must be disposed. Site cleanup activities throughout the U.S. Department of Energy (DOE) complex are projected to continue through 2050. Some of this waste is mixed waste (MW), containing both hazardous and radioactive components. In addition, there is a need for MW disposal from other mission activities. The Waste Management Programmatic Environmental Impact Statement Record of Decision designates the Nevada Test Site (NTS) as a regional MW disposal site. The NTS has a facility that is permitted to dispose of onsite- and offsite-generated MW until November 30, 2010. There is not a DOE waste management facility that is currently permitted to dispose of offsite-generated MW after 2010, jeopardizing the DOE environmental cleanup mission and other MW-generating mission-related activities. A mission needs document (CD-0) has been prepared for a newly permitted MW disposal facility at the NTS that would provide the needed capability to support DOE's environmental cleanup mission and other MW-generating mission-related activities. This report presents a conceptual engineering design for a MW facility that is fully compliant with Resource Conservation and Recovery Act (RCRA) and DOE O 435.1, 'Radioactive Waste Management'. The facility, which will be located within the Area 5 Radioactive Waste Management Site (RWMS) at the NTS, will provide an approximately 20,000-cubic yard waste disposal capacity. The facility will be licensed by the Nevada Division of Environmental Protection (NDEP).

  10. Portland General Electric Beaver synfuels project a coal gasification combined cycle methanol facility development program

    SciTech Connect

    Skov, E.R.; Yott, R.A.; Clancy, G.M.

    1981-01-01

    The Beaver coal gasification facility is currently undergoing preliminary engineering and feasibility analysis. Based on the existing 600 MW (nominal) Beaver combined cycle generating station and the adjacent plant site, which is eminently suitable for receiving and storage of subbituminous coal from either Alaska or Wyoming, a non-integrated CGCC facility combined with a methanol plant for increased utilization of the plant facilities and capital investment looks attractive for the 1987 time frame and forward. The CGCC facility would be environmentally benign since the gasification process inherently permits removal of essentially all sulfur, metals and particulate matter. The association with a methanol plant permits a high utilization factor of the overall CGCC-methanol facility. The beaver coal gasification facility will produce 60 billion Btu/day of MBG equivalent to about 300MWe, plus 1,750 Ton/D methanol, 10 million SCP/D SNG, nd 90 Ton/Day ammonia from about 11,000 Ton/Day subbituminous coal. The products are forecast to be competitively marketed in the region. The project could be implemented on a six year schedule, and a preliminary economic evaluation indicated that the products can be competitive with gas and oil for the 1988 time frame and beyond. 6 refs.

  11. Indianapolis resource recovery facility; Community efforts and technology required for a successful project

    SciTech Connect

    Stevens, P.L. ); Henderson, J.S. ); Tulli, R. )

    1990-01-01

    There are many community needs. Refuse is an abundant byproduct of our civilization. The disposal of this byproduct has become a major problem for our cities. This paper describes on community's efforts to turn a community problem, refuse disposal, into a community asset. The paper describes the many aspects of effort and technology required to develop the Indianapolis Resource Recovery Facility. This facility required the cooperation of the public and private sectors to blend technology into a successful project. Special efforts were required to match appropriate technology to specific community needs and produce a successful and economically sound project. Five basic activities are presented. The first four activities are essential steps for any community to assure the right project fit to community needs. The areas presented are: defining community needs, technology evaluation (approaches evaluated), feasibility studies (economic studies), project implementation (bids and contracts), and a description of the Indianapolis resource recovery facility. A review of these five areas places a real world perspective on refuse as an alternative fuel and source of resource recovery.

  12. Influence of computational fluid dynamics on experimental aerospace facilities: A fifteen year projection

    NASA Technical Reports Server (NTRS)

    1983-01-01

    An assessment was made of the impact of developments in computational fluid dynamics (CFD) on the traditional role of aerospace ground test facilities over the next fifteen years. With improvements in CFD and more powerful scientific computers projected over this period it is expected to have the capability to compute the flow over a complete aircraft at a unit cost three orders of magnitude lower than presently possible. Over the same period improvements in ground test facilities will progress by application of computational techniques including CFD to data acquisition, facility operational efficiency, and simulation of the light envelope; however, no dramatic change in unit cost is expected as greater efficiency will be countered by higher energy and labor costs.

  13. The Advanced Neutron Source (ANS) project: A world-class research reactor facility

    SciTech Connect

    Thompson, P.B.; Meek, W.E.

    1993-07-01

    This paper provides an overview of the Advanced Neutron Source (ANS), a new research facility being designed at Oak Ridge National Laboratory. The facility is based on a 330 MW, heavy-water cooled and reflected reactor as the neutron source, with a thermal neutron flux of about 7.5{times}10{sup 19}m{sup {minus}2}{center_dot}sec{sup {minus}1}. Within the reflector region will be one hot source which will serve 2 hot neutron beam tubes, two cryogenic cold sources serving fourteen cold neutron beam tubes, two very cold beam tubes, and seven thermal neutron beam tubes. In addition there will be ten positions for materials irradiation experiments, five of them instrumented. The paper touches on the project status, safety concerns, cost estimates and scheduling, a description of the site, the reactor, and the arrangements of the facilities.

  14. Recovery Act: Hydroelectric Facility Improvement Project - Replacement of Current Mechanical Seal System with Rope Packing System

    SciTech Connect

    Stephens, Jessica D.

    2013-05-29

    On January 27, 2010 the City of North Little Rock, Arkansas received notification of the awarding of a Department of Energy (DOE) grant totaling $450,000 in funding from the American Recovery and Reinvestment Act (ARRA) under the Project Title: Recovery Act: Hydroelectric Facility Improvement Project – Automated Intake Clearing Equipment and Materials Management. The purpose of the grant was for improvements to be made at the City’s hydroelectric generating facility located on the Arkansas River. Improvements were to be made through the installation of an intake maintenance device (IMD) and the purchase of a large capacity wood grinder. The wood grinder was purchased in order to receive the tree limbs, tree trunks, and other organic debris that collects at the intake of the plant during high flow. The wood grinder eliminates the periodic burning of the waste material that is cleared from the intake and reduces any additional air pollution to the area. The resulting organic mulch has been made available to the public at no charge. Design discussion and planning began immediately and the wood grinder was purchased in July of 2010 and immediately put to work mulching debris that was gathered regularly from the intake of the facility. The mulch is currently available to the public for free. A large majority of the design process was spent in discussion with the Corps of Engineers to obtain approval for drawings, documents, and permits that were required in order to make changes to the structure of the powerhouse. In April of 2011, the City’s Project Engineer, who had overseen the application, resigned and left the City’s employ. A new Systems Mechanical Engineer was hired and tasked with overseeing the project. The transfer of responsibility led to a re-examination of the original assumptions and research upon which the grant proposal was based. At that point, the project went under review and a trip was booked for July 2011 to visit facilities that currently

  15. Waste receiving and processing facility module 1 data management system software project management plan

    SciTech Connect

    Clark, R.E.

    1994-11-02

    This document provides the software development plan for the Waste Receiving and Processing (WRAP) Module 1 Data Management System (DMS). The DMS is one of the plant computer systems for the new WRAP 1 facility (Project W-026). The DMS will collect, store, and report data required to certify the low level waste (LLW) and transuranic (TRU) waste items processed at WRAP 1 as acceptable for shipment, storage, or disposal.

  16. The mixed waste management facility. Project baseline revision 1.2

    SciTech Connect

    Streit, R.D.; Throop, A.L.

    1995-04-01

    Revision 1.2 to the Project Baseline (PB) for the Mixed Waste Management Facility (MWMF) is in response to DOE directives and verbal guidance to (1) Collocate the Decontamination and Waste Treatment Facility (DWTF) and MWMF into a single complex, integrate certain and overlapping functions as a cost-saving measure; (2) Meet certain fiscal year (FY) new-BA funding objectives ($15.3M in FY95) with lower and roughly balanced funding for out years; (3) Reduce Total Project Cost (TPC) for the MWMF Project; (4) Include costs for all appropriate permitting activities in the project TPC. This baseline revision also incorporates revisions in the technical baseline design for Molten Salt Oxidation (MSO) and Mediated Electrochemical Oxidation (MEO). Changes in the WBS dictionary that are necessary as a result of this rebaseline, as well as minor title changes, at WBS Level 3 or above (DOE control level) are approved as a separate document. For completeness, the WBS dictionary that reflects these changes is contained in Appendix B. The PB, with revisions as described in this document, were also the basis for the FY97 Validation Process, presented to DOE and their reviewers on March 21-22, 1995. Appendix C lists information related to prior revisions to the PB. Several key changes relate to the integration of functions and sharing of facilities between the portion of the DWTF that will house the MWMF and those portions that are used by the Hazardous Waste Management (HWM) Division at LLNL. This collocation has been directed by DOE as a cost-saving measure and has been implemented in a manner that maintains separate operational elements from a safety and permitting viewpoint. Appendix D provides background information on the decision and implications of collocating the two facilities.

  17. 340 Facility Secondary Containment and Leak Detection Project W-302 Functional Design Criteria

    SciTech Connect

    Stordeur, R.T.

    1995-03-01

    This functional design criteria for the upgrade to the 340 radioactive liquid waste storage facility (Project W-302) specifically addresses the secondary containment issues at the current vault facility of the 340 Complex. This vault serves as the terminus for the Radioactive Liquid Waste System (RLWS). Project W-302 is necessary in order to bring this portion of the Complex into full regulatory compliance. The project title, ``340 Facility Secondary Containment and Leak Detection``, illustrates preliminary thoughts of taking corrective action directly upon the existing vault (such as removing the tanks, lining the vault, and replacing tanks). However, based on the conclusion of the engineering study, ``Engineering Study of the 300 Area Process Wastewater Handling System``, WHC-SD-WM-ER-277 (as well as numerous follow-up meetings with cognizant staff), this FDC prescribes a complete replacement of the current tank/vault system. This offers a greater array of tanks, and provides greater operating flexibility and ease of maintenance. This approach also minimizes disruption to RLWS services during ``tie-in``, as compared to the alternative of trying to renovate the old vault. The proposed site is within the current Complex area, and maintains the receipt of RLWS solutions through gravity flow.

  18. The Lead-Based VENUS-F Facility: Status of the FREYA Project

    NASA Astrophysics Data System (ADS)

    Kochetkov, Anatoly; Vittiglio, Guido; Wagemans, Jan; Uyttenhove, Wim; Krása, Antonín; Hernandez, Jérémie

    2016-02-01

    The GUINEVERE project in the 6th European Framework Program (FP6) [1] aimed to check the methods for sub-criticality monitoring. To execute the project, the water-moderated thermal VENUS facility was modified into the lead fast VENUS-F facility in the period 2007-2010. To prove the reliability of the reactivity monitoring methods, first of all a critical reference configuration was assembled and characterized by measurements of criticality, power distribution, and spectral indexes. These experiments were communicated for benchmarking at ISRD-14 [2]. The Monte Carlo MCNP 5-1.60 code with the JEFF 3.1.2 data library is used to perform simulations of the VENUS-F core, in particular to obtain Calculated-to-Experimental ratios (C/E) for fission rates and spectral indices. A sensitivity study is performed focusing on the impact of global and local parameters on C/E. In most cases C/E is close to unity within the uncertainties. Only a few exceptions were found, e.g. for the F28/F25 spectral index [3]. In order to investigate the discrepancies, a new measurement campaign with the same critical configuration was included in the currently ongoing FREYA project in FP7 [4]. The facility status, experimental plans, and the sensitivity study are presented in this paper.

  19. 49 CFR 195.59 - Abandonment or deactivation of facilities.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ..., operators may submit reports by mail, fax or e-mail to the Office of Pipeline Safety, Pipeline and Hazardous..., 1200 New Jersey Avenue, SE., Washington, DC 20590-0001; fax (202) 366-4566; e-mail,...

  20. 49 CFR 192.727 - Abandonment or deactivation of facilities.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... disconnected from all sources and supplies of gas; purged of gas; in the case of offshore pipelines, filled with water or inert materials; and sealed at the ends. However, the pipeline need not be purged when... supplies of gas; purged of gas; in the case of offshore pipelines, filled with water or inert...

  1. 49 CFR 195.59 - Abandonment or deactivation of facilities.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... System (NPMS) in accordance with the NPMS “Standards for Pipeline and Liquefied Natural Gas Operator... TRANSPORTATION OF HAZARDOUS LIQUIDS BY PIPELINE Annual, Accident, and Safety-Related Condition Reporting §...

  2. 49 CFR 195.59 - Abandonment or deactivation of facilities.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... System (NPMS) in accordance with the NPMS “Standards for Pipeline and Liquefied Natural Gas Operator... TRANSPORTATION OF HAZARDOUS LIQUIDS BY PIPELINE Annual, Accident, and Safety-Related Condition Reporting §...

  3. 49 CFR 195.59 - Abandonment or deactivation of facilities.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... System (NPMS) in accordance with the NPMS “Standards for Pipeline and Liquefied Natural Gas Operator... TRANSPORTATION OF HAZARDOUS LIQUIDS BY PIPELINE Annual, Accident, and Safety-Related Condition Reporting §...

  4. 49 CFR 195.59 - Abandonment or deactivation of facilities.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ....phmsa.dot.gov or contact the NPMS National Repository at 703-317-3073. A digital data format is... abandonment, and certification that, to the best of the operator's knowledge, all of the reasonably available information requested was provided and, to the best of the operator's knowledge, the abandonment was...

  5. 49 CFR 192.727 - Abandonment or deactivation of facilities.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... persons other than those authorized by the operator. (2) A mechanical device or fitting that will prevent... abandonment, diameter, method of abandonment, and certification that, to the best of the operator's knowledge, all of the reasonably available information requested was provided and, to the best of the...

  6. 49 CFR 192.727 - Abandonment or deactivation of facilities.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... persons other than those authorized by the operator. (2) A mechanical device or fitting that will prevent... abandonment, diameter, method of abandonment, and certification that, to the best of the operator's knowledge, all of the reasonably available information requested was provided and, to the best of the...

  7. 49 CFR 192.727 - Abandonment or deactivation of facilities.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... persons other than those authorized by the operator. (2) A mechanical device or fitting that will prevent... abandonment, diameter, method of abandonment, and certification that, to the best of the operator's knowledge, all of the reasonably available information requested was provided and, to the best of the...

  8. The ISOLDE facility and the HIE-HISOLDE project: Recent highlights

    SciTech Connect

    Borge, M. J. G.

    2014-07-23

    The ISOLDE facility at CERN has as objective the production, study and research of nuclei far from stability. The facility provides low energy radioactive beams and post-accelerated beams. In the last 45 years the ISOLDE facility has gathered unique expertise in research with radioactive beams. Over 700 isotopes of more than 70 elements have been used in a wide range of research domains, including cutting edge studies in nuclear structure, atomic physics, nuclear astrophysics, and fundamental interactions. These nuclear probes are also used to do frontier research in solid state and life sciences. There is an on-going upgrade of the facility, the HIE-ISOLDE project, which aims to improve the ISOLDE capabilities in a wide front, from an energy increase of the post-accelerated beam to improvements in beam quality and beam purity. The first phase of HIE-ISOLDE will start for physics in the autumn of 2015 with an upgrade of energy for all post-accelerated ISOLDE beams up to 5.5 MeV/u. In this contribution the most recent highlights of the facility are presented.

  9. Developing Renewable Energy Projects Larger Than 10 MWs at Federal Facilities

    SciTech Connect

    2013-03-01

    To accomplish Federal goals for renewable energy, sustainability, and energy security, large-scale renewable energy projects must be developed and constructed on Federal sites at a significant scale with significant private investment. For the purposes of this Guide, large-scale Federal renewable energy projects are defined as renewable energy facilities larger than 10 megawatts (MW) that are sited on Federal property and lands and typically financed and owned by third parties.1 The U.S. Department of Energy’s Federal Energy Management Program (FEMP) helps Federal agencies meet these goals and assists agency personnel navigate the complexities of developing such projects and attract the necessary private capital to complete them. This Guide is intended to provide a general resource that will begin to develop the Federal employee’s awareness and understanding of the project developer’s operating environment and the private sector’s awareness and understanding of the Federal environment. Because the vast majority of the investment that is required to meet the goals for large-scale renewable energy projects will come from the private sector, this Guide has been organized to match Federal processes with typical phases of commercial project development. FEMP collaborated with the National Renewable Energy Laboratory (NREL) and professional project developers on this Guide to ensure that Federal projects have key elements recognizable to private sector developers and investors. The main purpose of this Guide is to provide a project development framework to allow the Federal Government, private developers, and investors to work in a coordinated fashion on large-scale renewable energy projects. The framework includes key elements that describe a successful, financially attractive large-scale renewable energy project. This framework begins the translation between the Federal and private sector operating environments. When viewing the overall

  10. Project W-236A multi-function waste tank facility waste feed projections

    SciTech Connect

    Larrick, A.P.

    1994-12-22

    A review of Hanford Underground Waste Storage Tank Chemistry, coupled with planned remediation actions and retrieval sequences was conducted in order to predict the chemistry of the waste to be stored in the MWTF tanks. All projected waste solutions to be transferred to the MWTF tanks were found to be in compliance with current tank chemistry specifications; therefore, the waste and the tank materials of construction are expected to be compatible.

  11. Final deactivation report on the radioisotope production Lab-C, Building 3030, at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1997-08-01

    The purpose of this report is to document the condition of Bldg. 3030 completion of deactivation activities as outlined by the Department of Energy (DOE) Office of Nuclear Materials and Facility Stabilization Program (EM-60) guidance documentation. This report outlines the activities conducted to place the facility in a safe and environmentally sound condition for transfer to DOE`s Office of Environmental Restoration Program (EM-40). This report provides profile of Bldg. 3030 before and after deactivation activities. Turnover items, such as the Postdeactivation Surveillance & Maintenance Plan, remaining hazardous materials, radiological controls, Safeguards and Security, QA, facility operations, and supporting documentation provided in the Office of Nuclear Materials and Facility Stabilization Program (EM-60) Turnover package are discussed. Building 3030 will require access to facilitate required S&M activities to maintain the building safety envelope. Building 3030 was stabilized during deactivation so that when transferred to the EM-40 program, only a minimal S&M effort would be required to maintain the building`s safety envelope. Other than the minimal S&M activities, the building will be unoccupied and the exterior doors locked to prevent unauthorized access. The building will be entered only for required S&M. All materials have been removed from the building and the hot cell, and all utility systems, piping, and alarms have been deactivated.

  12. Computing conformational free energy by deactivated morphing.

    SciTech Connect

    Park, S.; Lau, A. Y.; Roux, B.; Univ. of Chicago

    2008-10-07

    Despite the significant advances in free-energy computations for biomolecules, there exists no general method to evaluate the free-energy difference between two conformations of a macromolecule that differ significantly from each other. A crucial ingredient of such a method is the ability to find a path between different conformations that allows an efficient computation of the free energy. In this paper, we introduce a method called 'deactivated morphing', in which one conformation is morphed into another after the internal interactions are completely turned off. An important feature of this method is the (shameless) use of nonphysical paths, which makes the method robustly applicable to conformational changes of arbitrary complexity.

  13. Evaluation of nuclear facility decommissioning projects. Project summary report, Elk River Reactor

    SciTech Connect

    Miller, R.L.; Adams, J.A.

    1982-12-01

    This report summarizes information concerning the decommissioning of the Elk River Reactor. Decommissioning data from available documents were input into a computerized data-handling system in a manner that permits specific information to be readily retrieved. The information is in a form that assists the Nuclear Regulatory Commission in its assessment of decommissioning alternatives and ALARA methods for future decommissionings projects. Samples of computer reports are included in the report. Decommissioning of other reactors, including NRC reference decommissioning studies, will be described in similar reports.

  14. Deactivation of free and stabilized acid phosphatase by urea.

    PubMed

    Gianfreda, L; Marrucci, G; Greco, G

    1986-11-01

    Tests on acid phosphatase (E.G. 3.1.3.2) deactivation by urea have been performed at two pH values. Two conditions have been used: native enzyme operating batch-wise in dilute solution and stabilized enzyme in continuous flow ultrafiltration membrane reactor. Stabilization is achieved by confining the enzyme within a concentrated solution of a linear chain polymer that forms a polarization layer over the membrane. The results provide significant information on the kinetics and thermodynamics of the complex phenomena taking place during deactivation. Deactivation by urea is also compared with thermal deactivation. PMID:18555278

  15. Purdue University National Biomedical Tracer Facility: Project definition phase. Final report

    SciTech Connect

    Green, M.A.

    1995-02-15

    The proposed National Biomedical Tracer Facility (NBTF) will house a high-current accelerator dedicated to production of short-lived radionuclides for biomedical and scientific research. The NBTF will play a vital role in repairing and maintaining the United States` research infrastructure for generation of essential accelerator-based radioisotopes. If properly designed and managed, the NBTF should also achieve international recognition as a Center-of-Excellence for research on radioisotope production methods and for associated education and training. The current report documents the results of a DOE-funded NBTF Project Definition Phase study carried out to better define the technical feasibility and projected costs of establishing and operating the NBTF. This report provides an overview of recommended Facility Design and Specifications, including Accelerator Design, Building Design, and the associated Construction Cost Estimates and Schedule. It is recommended that the NBTF be established as an integrated, comprehensive facility for meeting the diverse production, research, and educational missions set forth in previous documents. Based on an analysis of the projected production demands that will be placed on the NBTF, it appears that a 70 MeV, 1 mA, negative ion cyclotron will offer a good balance between production capabilities and the costs of accelerator purchase and operation. A preliminary architectural plan is presented for a facility designed specifically to fulfill the functions of the NBTF in a cost-effective manner. This report also presents a detailed analysis of the Required Federal State, and Local Permits that may be needed to establish the NBTF, along with schedules and cost estimates for obtaining these permits. The Handling, Storage, and Disposal of Radioactive Waste will pose some significant challenges in the operation of the NBTF, but at this stage of planning the associated problems do not appear to be prohibitive.

  16. PNC/DOE Remote Monitoring Project at Japan`s Joyo Facility

    SciTech Connect

    Ross, M.; Hashimoto, Yu; Senzaki, Masao; Shigeto, Toshinori; Sonnier, C.; Dupree, S.; Ystesund, K.; Hale, W.

    1996-07-25

    The Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan and the US Department of Energy (DOE) are cooperating on the development of a remote monitoring system for nuclear nonproliferation efforts. This cooperation is part of a broader safeguards agreement between PNC and DOE. A remote monitoring system is being installed in a spent fuel storage area at PNC`s experimental reactor facility Joyo in Oarai. The system has been designed by Sandia National Laboratories (SNL) and is closely related to those used in other SNL remote monitoring projects. The Joyo project will particularly study the unique aspects of remote monitoring in contribution to nuclear nonproliferation. The project will also test and evaluate the fundamental design and implementation of the remote monitoring system in its application to regional and international safeguards efficiency. This paper will present a short history of the cooperation, the details of the monitoring system and a general schedule of activities.

  17. Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron Activated Shield Wall

    SciTech Connect

    Michael R. Kruzic

    2007-09-16

    Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility was used in the early to mid-1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles in the immediate area. Identified as Corrective Action Unit 115, the TCA facility was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the ''Federal Facility Agreement and Consent Order''. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously provided technical decisions are made by an experienced decision maker within the site conceptual site model, identified in the Data Quality Objective process. Facility closure involved a seven-step decommissioning strategy. Key lessons learned from the project included: (1) Targeted preliminary investigation activities provided a more solid technical approach, reduced surprises and scope creep, and made the working environment safer for the D&D worker. (2) Early identification of risks and uncertainties provided opportunities for risk management and mitigation planning to address challenges and unanticipated conditions. (3) Team reviews provided an excellent mechanism to consider all aspects of the task, integrated safety into activity performance, increase team unity and ''buy-in'' and promoted innovative and time saving ideas. (4) Development of CED protocols ensured safety and control. (5) The same proven D&D strategy is now being employed on the larger ''sister'' facility, Test Cell C.

  18. Dismantlement and decontamination of a plutonium-238 facility at the Savannah river site

    SciTech Connect

    Smith, R.H.; Hootman, H.E.

    1994-01-01

    Very little documented decontamination and decommissioning (D&D) experience exists on which to project cleanup costs and schedules for plutonium facilities at DOE sites. A plutonium-238 processing facility at Savannah River Site (SRS) has been undergoing D&D intermittently since 1984. Although this cleanup effort was not originally intended to quantify results, some key data have been accumulated, and the project has demonstrated effective methods of performing D&D work under conditions of high contamination. Some data is presented here; however, more specific tests and data may be obtained during the remainder of this project. This project has been recommended as a candidate test facility for a DOE planned {open_quotes}Integrated D&D Demonstration{close_quotes} managed by EM-50 to develop and demonstrate technology for D&D and surplus facilities deactivation.

  19. Antioxidant Deactivation on Graphenic Nanocarbon Surfaces

    SciTech Connect

    Liu, Xinyuan; Sen, Sujat; Liu, Jingyu; Kulaots, Indrek; Geohegan, David B; Kane, Agnes; Puretzky, Alexander A; Rouleau, Christopher M; More, Karren Leslie; Palmore, G. Tayhas R.; Hurt, Robert H.

    2011-01-01

    This article reports a direct chemical pathway for antioxidant deactivation on the surfaces of carbon nanomaterials. In the absence of cells, carbon nanotubes are shown to deplete the key physiological antioxidant glutathione (GSH) in a reaction involving dissolved dioxygen that yields the oxidized dimer, GSSG, as the primary product. In both chemical and electrochemical experiments, oxygen is only consumed at a significant steady-state rate in the presence of both nanotubes and GSH. GSH deactivation occurs for single- and multi-walled nanotubes, graphene oxide, nanohorns, and carbon black at varying rates that are characteristic of the material. The GSH depletion rates can be partially unified by surface area normalization, are accelerated by nitrogen doping, and suppressed by defect annealing or addition of proteins or surfactants. It is proposed that dioxygen reacts with active sites on graphenic carbon surfaces to produce surface-bound oxygen intermediates that react heterogeneously with glutathione to restore the carbon surface and complete a catalytic cycle. The direct catalytic reaction between nanomaterial surfaces and antioxidants may contribute to oxidative stress pathways in nanotoxicity, and the dependence on surface area and structural defects suggest strategies for safe material design.

  20. Surrogate burns in deactivation furnace system.

    PubMed

    Shah, J K

    1999-05-14

    The deactivation furnace system at the Deseret Chemical Depot in Utah is designed for processing explosive components from munitions containing nerve and mustard agents. The system was installed during the period of 1989 through 1993. The Utah Division of Solid and Hazardous Waste (UDSHW) required that trial burns be conducted using surrogate chemicals prior to introducing chemical agents into the system. The selected surrogate chemicals were monochlorobenzene and hexachloroethane based on the criteria established by the UDSHW. Three surrogate runs were conducted in October, 1995. The gaseous emissions and liquid and solid effluents were sampled and analyzed using approved EPA methods. The trial burns demonstrated the desirable destruction and removal efficiency for the selected surrogate chemicals. The pollution abatement system demonstrated the desired scrubbing efficiency for acid gases generated during incineration of chlorinated surrogate chemicals. The particulate removal efficiency during the trial burns was also considerably higher than required by regulations. After comprehensive review of the performance of the deactivation furnace system during the surrogate trial burns, UDSHW approved introduction of GB nerve agent into the system to prepare it for agent trial burns. PMID:10334826

  1. Antioxidant deactivation on graphenic nanocarbon surfaces

    PubMed Central

    Liu, Xinyuan; Sen, Sujat; Liu, Jingyu; Kulaots, Indrek; Geohegan, David; Kane, Agnes; Puretzky, Alex A.; Rouleau, Christopher M.; More, Karren L.; Palmore, G. Tayhas R.; Hurt, Robert H.

    2013-01-01

    This article reports a direct chemical pathway for antioxidant deactivation on the surfaces of carbon nanomaterials. In the absence of cells, carbon nanotubes are shown to deplete the key physiological antioxidant glutathione (GSH) in a reaction involving dissolved dioxygen that yields the oxidized dimer, GSSG, as the primary product. In both chemical and electrochemical experiments, oxygen is only consumed at a significant steady-state rate in the presence of both nanotubes and GSH. GSH deactivation occurs for single- and multi-walled nanotubes, graphene oxide, nanohorns, and carbon black at varying rates that are characteristic of the material. The GSH depletion rates can be partially unified by surface area normalization, are accelerated by nitrogen doping, and suppressed by defect annealing or addition of proteins or surfactants. We propose that dioxygen reacts with active sites on graphenic carbon surfaces to produce surface-bound oxygen intermediates that react heterogeneously with glutathione to restore the carbon surface and complete a catalytic cycle. The direct catalytic reaction between nanomaterial surfaces and antioxidants may contribute to oxidative stress pathways in nanotoxicity, and the dependence on surface area and structural defects suggest strategies for safe material design. PMID:21818846

  2. Compressed Air System Renovation Project Improves Production at a Food Processing Facility (Mead-Johnson Nutritionals, Bristol-Myers Squib)

    SciTech Connect

    2001-06-01

    This case study is one in a series on industrial firms who are implementing energy efficient technologies and system improvements into their manufacturing processes. This case study documents the activities, savings, and lessons learned on the food processing facility project.

  3. 75 FR 5626 - Cle Elum Dam Fish Passage Facilities and Fish Reintroduction Project; Kittitas County, WA INT-DES...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-03

    ... of Reclamation (Reclamation) published a notice in the Federal Register on April 8, 2009 (74 FR 16007... Fish Passage Facilities and Fish Reintroduction Project. The Washington State Department of Ecology...

  4. Healy Clean Coal Project: Healy coal firing at TRW Cleveland Test Facility. Final report

    SciTech Connect

    Koyama, T.; Petrill, E.; Sheppard, D.

    1991-08-01

    A test burn of two Alaskan coals was conducted at TRW`s Cleveland test facility in support of the Healy Clean Coal Project, as part of Clean Coal Technology III Program in which a new power plant will be constructed using a TRW Coal Combustion System. This system features ash slagging technology combined with NO{sub x} and SO{sub x} control. The tests, funded by the Alaska Industrial Development and Export Authority (AIDEA) and TRW, were conducted to verify that the candidate Healy station coals could be successfully fired in the TRW coal combustor, to provide data required for scale-up to the utility project size requirements, and to produce sufficient flash-calcined material (FCM) for spray dryer tests to be conducted by Joy/NIRO. The tests demonstrated that both coals are viable candidates for the project, provided the data required for scale-up, and produced the FCM material. This report describes the modifications to the test facility which were required for the test burn, the tests run, and the results of the tests.

  5. Healy Clean Coal Project: Healy coal firing at TRW Cleveland Test Facility

    SciTech Connect

    Koyama, T.; Petrill, E.; Sheppard, D.

    1991-08-01

    A test burn of two Alaskan coals was conducted at TRW's Cleveland test facility in support of the Healy Clean Coal Project, as part of Clean Coal Technology III Program in which a new power plant will be constructed using a TRW Coal Combustion System. This system features ash slagging technology combined with NO{sub x} and SO{sub x} control. The tests, funded by the Alaska Industrial Development and Export Authority (AIDEA) and TRW, were conducted to verify that the candidate Healy station coals could be successfully fired in the TRW coal combustor, to provide data required for scale-up to the utility project size requirements, and to produce sufficient flash-calcined material (FCM) for spray dryer tests to be conducted by Joy/NIRO. The tests demonstrated that both coals are viable candidates for the project, provided the data required for scale-up, and produced the FCM material. This report describes the modifications to the test facility which were required for the test burn, the tests run, and the results of the tests.

  6. 39 CFR 778.8 - How does the Postal Service provide states an opportunity to comment on proposed facility project...

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 39 Postal Service 1 2014-07-01 2014-07-01 false How does the Postal Service provide states an opportunity to comment on proposed facility project actions? 778.8 Section 778.8 Postal Service UNITED STATES POSTAL SERVICE SPECIAL REGULATIONS INTERGOVERNMENTAL REVIEW OF POSTAL SERVICE FACILITY ACTIONS §...

  7. 39 CFR 778.3 - What categories of facility project actions of the Postal Service are subject to these regulations?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 39 Postal Service 1 2014-07-01 2014-07-01 false What categories of facility project actions of the Postal Service are subject to these regulations? 778.3 Section 778.3 Postal Service UNITED STATES POSTAL SERVICE SPECIAL REGULATIONS INTERGOVERNMENTAL REVIEW OF POSTAL SERVICE FACILITY ACTIONS § 778.3...

  8. 39 CFR 778.8 - How does the Postal Service provide states an opportunity to comment on proposed facility project...

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 39 Postal Service 1 2012-07-01 2012-07-01 false How does the Postal Service provide states an opportunity to comment on proposed facility project actions? 778.8 Section 778.8 Postal Service UNITED STATES POSTAL SERVICE SPECIAL REGULATIONS INTERGOVERNMENTAL REVIEW OF POSTAL SERVICE FACILITY ACTIONS §...

  9. 39 CFR 778.8 - How does the Postal Service provide states an opportunity to comment on proposed facility project...

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 39 Postal Service 1 2011-07-01 2011-07-01 false How does the Postal Service provide states an opportunity to comment on proposed facility project actions? 778.8 Section 778.8 Postal Service UNITED STATES POSTAL SERVICE SPECIAL REGULATIONS INTERGOVERNMENTAL REVIEW OF POSTAL SERVICE FACILITY ACTIONS §...

  10. 39 CFR 778.8 - How does the Postal Service provide states an opportunity to comment on proposed facility project...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 39 Postal Service 1 2010-07-01 2010-07-01 false How does the Postal Service provide states an opportunity to comment on proposed facility project actions? 778.8 Section 778.8 Postal Service UNITED STATES POSTAL SERVICE SPECIAL REGULATIONS INTERGOVERNMENTAL REVIEW OF POSTAL SERVICE FACILITY ACTIONS §...

  11. 39 CFR 778.3 - What categories of facility project actions of the Postal Service are subject to these regulations?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 39 Postal Service 1 2012-07-01 2012-07-01 false What categories of facility project actions of the Postal Service are subject to these regulations? 778.3 Section 778.3 Postal Service UNITED STATES POSTAL SERVICE SPECIAL REGULATIONS INTERGOVERNMENTAL REVIEW OF POSTAL SERVICE FACILITY ACTIONS § 778.3...

  12. 39 CFR 778.3 - What categories of facility project actions of the Postal Service are subject to these regulations?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 39 Postal Service 1 2011-07-01 2011-07-01 false What categories of facility project actions of the Postal Service are subject to these regulations? 778.3 Section 778.3 Postal Service UNITED STATES POSTAL SERVICE SPECIAL REGULATIONS INTERGOVERNMENTAL REVIEW OF POSTAL SERVICE FACILITY ACTIONS § 778.3...

  13. 39 CFR 778.3 - What categories of facility project actions of the Postal Service are subject to these regulations?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 39 Postal Service 1 2010-07-01 2010-07-01 false What categories of facility project actions of the Postal Service are subject to these regulations? 778.3 Section 778.3 Postal Service UNITED STATES POSTAL SERVICE SPECIAL REGULATIONS INTERGOVERNMENTAL REVIEW OF POSTAL SERVICE FACILITY ACTIONS § 778.3...

  14. 39 CFR 778.3 - What categories of facility project actions of the Postal Service are subject to these regulations?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 39 Postal Service 1 2013-07-01 2013-07-01 false What categories of facility project actions of the Postal Service are subject to these regulations? 778.3 Section 778.3 Postal Service UNITED STATES POSTAL SERVICE SPECIAL REGULATIONS INTERGOVERNMENTAL REVIEW OF POSTAL SERVICE FACILITY ACTIONS § 778.3...

  15. 39 CFR 778.8 - How does the Postal Service provide states an opportunity to comment on proposed facility project...

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 39 Postal Service 1 2013-07-01 2013-07-01 false How does the Postal Service provide states an opportunity to comment on proposed facility project actions? 778.8 Section 778.8 Postal Service UNITED STATES POSTAL SERVICE SPECIAL REGULATIONS INTERGOVERNMENTAL REVIEW OF POSTAL SERVICE FACILITY ACTIONS §...

  16. Highlights of the ISOLDE facility and the HIE-ISOLDE Project

    NASA Astrophysics Data System (ADS)

    Borge, M. J. G.

    2016-05-01

    The ISOLDE Radioactive Beam Facility is the dedicated CERN installation for the production and acceleration of radioactive nuclei far from stability. Exotic nuclei of most chemical elements are available for the study of nuclear structure, nuclear astrophysics, fundamental symmetries and atomic physics, as well as for applications in condensed-matter and life sciences. Since more than a decade it offers the largest variety of post-accelerated radioactive beams in the world today. In order to broaden the scientific opportunities beyond the reach of the present facility, the on-going HIE-ISOLDE (High Intensity and Energy) project will provide major improvements in energy range, beam intensity and beam quality. Post-accelerated beams will be available already this year boosting the beam energy of the current REX LINAC to 4.3 MeV/u reaching 5.5 MeV/u next spring. In this new energy regime the Coulomb excitation cross sections are strongly increased with respect to the previous energy of bearly 3 MeV/u and many transfer reaction channels will open. The second stage of the energy upgrade will allow energies of the beam up to 10 MeV/u for the worst scenario of A/q = 4.5. The funds are already secured and it is expected to be completed in 2017. In this contribution the present status of the ISOLDE facility will be discussed, some highlights will be briefly described to illustrate the advances of the facility. The HIEISOLDE project will be described together with a panorama of the physics cases to be addressed in the near future with emphasis in the day-one experiment to be done this year.

  17. A new starting point-the renewal project of chinese balloon facility

    NASA Astrophysics Data System (ADS)

    Yidong, Gu

    To meet the increasing requirements of scientific investigation by using balloons, Chinese Balloon Facility is carrying out a project to get the additional equipment with high performance, improve the existing facilities since 1995. Besides, because of the development of civil aviation in recent years, to meet the requirement of the authority of air traffic control, the Chinese balloon launch station at Xiang He must be moved to a new place. It is just an opportune moment to make a future program for Chinese scientific ballooning. The investigations and choices to a new launch site is in progress. We call these an Renewal Project of Chinese balloon Facility. It will be accomplished in 1997. The items of new manufactured and improved equipment involve: A new launch vehicle with launch capacity of 2 tons payload for dynamic launch. A new down-link data telecommunication system with bit rate of 256 Kbps. Improvements of the telemetry & tracking and telecommand facilities. To enlarge the storage of the amount of the lift gas To increase the carrying capacity of the recovery parachute. The candidates of the new launch site are located at Gu Cheng (37 deg47' N, 116 deg08' E) and Zheng Ding (38 deg30'N, 114 deg57'E), Hebei Province of China. One of them will be used for testing flights from Jun.,1997. The comprehensive conditions to air traffic control, the flight duration and recovery operations are expected to be considerably improved. The continuous efforts to improve the balloon film and to develop larger balloons were made for years. It is also described in this paper.

  18. RCRA (Resource Conservation and Recovery Act) ground-water monitoring projects for Hanford facilities: Annual progress report for 1988

    SciTech Connect

    Fruland, R.M.; Lundgren, R.E.

    1989-04-01

    This report describes the progress during 1988 of 14 Hanford Site ground-water monitoring projects covering 16 hazardous waste facilities and 1 nonhazardous waste facility (the Solid Waste Landfill). Each of the projects is being conducted according to federal regulations based on the Resource Conservation and Recovery Act (RCRA) of 1976 and the State of Washington Administrative Code. 21 refs., 23 figs., 8 tabs.

  19. 10 CFR 218.2 - Activation/Deactivation.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 3 2011-01-01 2011-01-01 false Activation/Deactivation. 218.2 Section 218.2 Energy DEPARTMENT OF ENERGY OIL STANDBY MANDATORY INTERNATIONAL OIL ALLOCATION General Provisions § 218.2 Activation/Deactivation. (a) This rule shall take effect providing: (1) The International Energy Program has been activated; and, (2) The President...

  20. 10 CFR 218.2 - Activation/Deactivation.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 3 2010-01-01 2010-01-01 false Activation/Deactivation. 218.2 Section 218.2 Energy DEPARTMENT OF ENERGY OIL STANDBY MANDATORY INTERNATIONAL OIL ALLOCATION General Provisions § 218.2 Activation/Deactivation. (a) This rule shall take effect providing: (1) The International Energy Program has...

  1. 10 CFR 218.2 - Activation/Deactivation.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 3 2013-01-01 2013-01-01 false Activation/Deactivation. 218.2 Section 218.2 Energy DEPARTMENT OF ENERGY OIL STANDBY MANDATORY INTERNATIONAL OIL ALLOCATION General Provisions § 218.2 Activation/Deactivation. (a) This rule shall take effect providing: (1) The International Energy Program has...

  2. 10 CFR 218.2 - Activation/Deactivation.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 3 2014-01-01 2014-01-01 false Activation/Deactivation. 218.2 Section 218.2 Energy DEPARTMENT OF ENERGY OIL STANDBY MANDATORY INTERNATIONAL OIL ALLOCATION General Provisions § 218.2 Activation/Deactivation. (a) This rule shall take effect providing: (1) The International Energy Program has...

  3. 10 CFR 218.2 - Activation/Deactivation.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 3 2012-01-01 2012-01-01 false Activation/Deactivation. 218.2 Section 218.2 Energy DEPARTMENT OF ENERGY OIL STANDBY MANDATORY INTERNATIONAL OIL ALLOCATION General Provisions § 218.2 Activation/Deactivation. (a) This rule shall take effect providing: (1) The International Energy Program has...

  4. 46 CFR 315.11 - Vessel deactivation procedures.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 46 Shipping 8 2011-10-01 2011-10-01 false Vessel deactivation procedures. 315.11 Section 315.11... AGREEMENTS AND APPPOINTMENT OF AGENTS § 315.11 Vessel deactivation procedures. When an Agent is responsible as vessel operator to decommission and deliver a vessel to the NDRF, that Agent shall observe all...

  5. US Department of Energy Grand Junction Projects Office Remedial Action Project. Final report of the decontamination and decommissioning of Building 52 at the Grand Junction Projects Office Facility

    SciTech Connect

    Krabacher, J.E.

    1996-08-01

    The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, also was the remedial action contractor. Building 52 was found to be radiologically contaminated and was demolished in 1994. The soil area within the footprint of the building has been remediated in accordance with the identified standards and the area can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.

  6. Materials sciences research. [research facilities, research projects, and technical reports of materials tests

    NASA Technical Reports Server (NTRS)

    1973-01-01

    Research projects involving materials research conducted by various international test facilities are reported. Much of the materials research is classified in the following areas: (1) acousto-optic, acousto-electric, and ultrasonic research, (2) research for elucidating transport phenomena in well characterized oxides, (3) research in semiconductor materials and semiconductor devices, (4) the study of interfaces and interfacial phenomena, and (5) materials research relevant to natural resources. Descriptions of the individual research programs are listed alphabetically by the name of the author and show all personnel involved, resulting publications, and associated meeting speeches.

  7. Integrated disposal Facility Sagebrush Habitat Mitigation Project: FY2007 Compensation Area Monitoring Report

    SciTech Connect

    Durham, Robin E.; Sackschewsky, Michael R.

    2007-09-01

    This report summarizes the first year survival of sagebrush seedlings planted as compensatory mitigation for the Integrated Disposal Facility Project. Approximately 42,600 bare root seedlings and 26,000 pluglings were planted at a mitigation site along Army Loop Road in February 2007. Initial baseline monitoring occurred in March 2007, and first summer survival was assessed in September 2007. Overall survival was 19%, with bare root survival being marginally better than pluglings (21% versus 14%). Likely major factors contributing to low survival were late season planting and insufficient soil moisture during seedling establishment.

  8. Planning and managing future space facility projects. [management by objectives and group dynamics

    NASA Technical Reports Server (NTRS)

    Sieber, J. E.; Wilhelm, J. A.; Tanner, T. A.; Helmreich, R. L.; Burgenbauch, S. F.

    1979-01-01

    To learn how ground-based personnel of a space project plan and organize their work and how such planning and organizing relate to work outcomes, longitudinal study of the management and execution of the Space Lab Mission Development Test 3 (SMD 3) was performed at NASA Ames Research Center. A view of the problems likely to arise in organizations and some methods of coping with these problems are presented as well as the conclusions and recommendations that pertain strictly to SMD 3 management. Emphasis is placed on the broader context of future space facility projects and additional problems that may be anticipated. A model of management that may be used to facilitate problem solving and communication - management by objectives (MBO) is presented. Some problems of communication and emotion management that MBO does not address directly are considered. Models for promoting mature, constructive and satisfying emotional relationships among group members are discussed.

  9. Portuguese waste-to energy project: Work moves ahead on `showcase` facility

    SciTech Connect

    Schroppe, J.T.

    1997-12-31

    With the disposal of growing amounts of municipal solid waste becoming an increasing concern for governmental authorities around the world the waste-to-energy project being built in Portugal, just north of Lisbon, may well serve as a showcase for one approach to the efficient disposal of MSW. The plant is being designed, engineered and built by Grupo Progresso Foster Wheeler, a joint-venture team of Foster Wheeler Power Systems, Inc. and Foster Wheeler Conception Etudes Entretien. One of the largest such plants in the world when completed, the facility will use three waste-combustion systems (with capability for adding a fourth) to burn 2016 metric tonnes of refuse per day. In this article J. Thomas Schroppe, Executive Vice President of Foster Wheeler Power Systems, Inc., provides an overview of the current waste-to-energy market and discusses the Portuguese project in detail.

  10. Initial deactivation of residue hydrodemetallization catalysts

    SciTech Connect

    Gualda, G.; Kasztelan, S.

    1996-06-01

    Used NiMo/alumina residue hydrodemetallization catalysts with bimodal pore size distribution have been prepared in batch and continuous flow reactors using a Safanyia atmospheric residue. The batch reactor provided used catalysts containing carbon deposits with almost no metal deposits (less than 200 ppm V and 4 to 15 wt% C), whereas the continuous flow reactor provided used catalysts containing both metal and carbon deposits (up to 1.3 wt% V and 11 to 14 wt% C). Used catalyst elemental analysis indicates that within experimental uncertainties the carbon deposits have a density of 1.5 {plus_minus} 0.2 g/cm{sup 3} and contain sulfur, nitrogen, and hydrogen, with different H/C ratio, the latter of depending on both the experimental conditions and the amount of carbon. Characterization of the used catalysts by electron probe microanalysis, secondary ion mass spectrometry, X-ray photoelectron spectroscopy. X-ray diffraction, transmission electron microscopy, and porosimetry show that V and C were well distributed in the catalyst grain in most of the samples and that carbon deposits are best described by three-dimensional patches of amorphous carbon (young coke) which generate pore size restrictions. Both carbon and vanadium have a deactivating effect on toluene hydrogenation, cyclohexane isomerization, and thiophene hydrodesulfurization performed on used catalysts under 6 MPa hydrogen pressure. However, a small amount of vanadium well dispersed inside the catalyst grain has been found to be more deactivating than a large amount of carbon. 71 refs., 17 figs., 6 tabs.

  11. Progress with the 2Q-LEBT facility for the RIA project.

    SciTech Connect

    Vinogradov, N.; Aseev, V. N.; Kern, M. R. L.; Ostroumov, P. N.; Pardo, R. C.; Scott, R.; Physics

    2005-01-01

    The design goal of 400 kW uranium beam in the Rare Isotope Accelerator (RIA) Driver Linac can be achieved employing a concept of simultaneous acceleration of two charge states. It has been undertaken to build a prototype 2Q-injector of the RIA Driver Linac which includes an ECR ion source, a LEBT and one-segment of the prototype RFQ. The project called the 2Q-LEBT Facility is being developed in the Physics Division of ANL. Currently, the 2Q-LEBT Facility consists of BIE-100 ECR ion source. The reassembly and commissioning of the source has been completed. During the commissioning process we redesigned and manufactured a few components of the source to increase the beam production performance. A new diagnostic station has been designed and built for accurate measurements of the output beam emittance. The further development of the 2Q-LEBT Facility comprises installation of the source on 100 kV high-voltage platform, building an achromatic bending and transport system including the multi-harmonic buncher, and a full power 57.5 MHz RFQ segment. This report includes a detailed description of the 2Q-LEBT design and beam dynamics simulations along with emittance measurements for various beams.

  12. Environmental Restoration Program pollution prevention checklist guide for the facility characterization project phase

    SciTech Connect

    Not Available

    1993-09-01

    A facility characterization (FC) is conducted to determine the nature and extent contamination at a potential hazardous facility waste site. The information gathered during an FC includes (1) data on the volume and chemical nature of the waste, (2) information on the extent of contamination and the migration potential of the contaminants, (3) preliminary information on evaluation of alternative concepts that can or cannot be considered, and (4)supportive technical and cost data. For the purposes of identification, the following operational phases will be used for definition for this phase of the decommissioning and decontamination process (1) facility characterization before clean up, (2) characterization during clean up, (3) characterization of waste materials, and (4) site characterization after clean up. A key consideration in this process is the prevention of any waste to be generated from these characterization activities. The purpose of this checklist guide is to assist users with incorporating pollution prevention/waste minimization (PP/WM) in all FC phase projects of the Environmental Restoration (ER) Program. This guide will help users document PP/WM activities for technology transfer and reporting requirements. Automated computer screens will be created from the checklist data to assist users with implementing and evaluating waste reduction.

  13. Detailed information on the FGD retrofit project in Jaenschwalde and the FGD facility in Schwarze Pumpe

    SciTech Connect

    Friede, H.; Nass, K.H.; Breuer, H.

    1995-06-01

    VEAG, the newly founded company for supraregional power generation and distribution in eastern Germany, is retrofitting certain power plants with flue-gas desulfurization (FGD) facilities. Lignite is used almost exclusively as fuel in these power plants. Following German unification, the pollution control regulations in force in the Federal Republic of Germany also apply to the power plants operated by VEAG. The decision was made in principle to only build FGDs which are based on the proven limestone scrubbing process and produce recyclable gypsum as the end product. Experience accumulated with FGDs in lignite-fired power plants resulted in a new concept, which elaborated in cooperation with the commissioned consultants (including Siemens/KWU). This paper will present using the example of a new power plant project with FGD - the 2 x 800-MW power plant Schwarze Pumpe - and an FGD retrofit - the 3 x 1000-MW power plant Janschwalde - the salient features of these facilities (full-metal scrubbers, slurry-carrying pipework and treated-flue-gas ducts made of FRP, flue-gas heat recovery, fine-grained solids separation to improve gypsum quality, use of FGD wastewater for ash moistening and gypsum recycling), an overview of the design as well as construction progress and scheduling. The two FGD facilities are being supplied by KRC/Noell and operate on a two-circuit principle.

  14. Annual report for RCRA groundwater monitoring projects at Hanford Site facilities for 1993

    SciTech Connect

    Not Available

    1994-02-01

    This report presents the annual hydrogeologic evaluation of 20 Resource Conservation and Recovery Act of 1976 groundwater monitoring projects and 1 nonhazardous waste facility at the US Department of Energy`s Hanford Site. Most of the projects no longer receive dangerous waste; a few projects continue to receive dangerous waste constituents for treatment, storage, or disposal. The 20 RCRA projects comprise 30 waste management units. Ten of the units are monitored under groundwater quality assessment status because of elevated levels of indicator parameters. The impact of those units on groundwater quality, if any, is being investigated. If dangerous waste or waste constituents have entered groundwater, their concentration, distribution, and rate of migration are evaluated. Groundwater is monitored at the other 20 units to detect contamination, should it occur. This report provides an interpretation of groundwater data collected at the waste management units between October 1992 and September 1993. Recent groundwater quality is also described for the 100, 200, 300, and 600 Areas and for the entire Hanford Site. Widespread contaminants include nitrate, chromium, carbon tetrachloride, tritium, and other radionuclides.

  15. Optimizing charge breeding techniques for ISOL facilities in Europe: Conclusions from the EMILIE project.

    PubMed

    Delahaye, P; Galatà, A; Angot, J; Cam, J F; Traykov, E; Ban, G; Celona, L; Choinski, J; Gmaj, P; Jardin, P; Koivisto, H; Kolhinen, V; Lamy, T; Maunoury, L; Patti, G; Thuillier, T; Tarvainen, O; Vondrasek, R; Wenander, F

    2016-02-01

    The present paper summarizes the results obtained from the past few years in the framework of the Enhanced Multi-Ionization of short-Lived Isotopes for Eurisol (EMILIE) project. The EMILIE project aims at improving the charge breeding techniques with both Electron Cyclotron Resonance Ion Sources (ECRIS) and Electron Beam Ion Sources (EBISs) for European Radioactive Ion Beam (RIB) facilities. Within EMILIE, an original technique for debunching the beam from EBIS charge breeders is being developed, for making an optimal use of the capabilities of CW post-accelerators of the future facilities. Such a debunching technique should eventually resolve duty cycle and time structure issues which presently complicate the data-acquisition of experiments. The results of the first tests of this technique are reported here. In comparison with charge breeding with an EBIS, the ECRIS technique had lower performance in efficiency and attainable charge state for metallic ion beams and also suffered from issues related to beam contamination. In recent years, improvements have been made which significantly reduce the differences between the two techniques, making ECRIS charge breeding more attractive especially for CW machines producing intense beams. Upgraded versions of the Phoenix charge breeder, originally developed by LPSC, will be used at SPES and GANIL/SPIRAL. These two charge breeders have benefited from studies undertaken within EMILIE, which are also briefly summarized here. PMID:26932063

  16. Optimizing charge breeding techniques for ISOL facilities in Europe: Conclusions from the EMILIE project

    NASA Astrophysics Data System (ADS)

    Delahaye, P.; Galatà, A.; Angot, J.; Cam, J. F.; Traykov, E.; Ban, G.; Celona, L.; Choinski, J.; Gmaj, P.; Jardin, P.; Koivisto, H.; Kolhinen, V.; Lamy, T.; Maunoury, L.; Patti, G.; Thuillier, T.; Tarvainen, O.; Vondrasek, R.; Wenander, F.

    2016-02-01

    The present paper summarizes the results obtained from the past few years in the framework of the Enhanced Multi-Ionization of short-Lived Isotopes for Eurisol (EMILIE) project. The EMILIE project aims at improving the charge breeding techniques with both Electron Cyclotron Resonance Ion Sources (ECRIS) and Electron Beam Ion Sources (EBISs) for European Radioactive Ion Beam (RIB) facilities. Within EMILIE, an original technique for debunching the beam from EBIS charge breeders is being developed, for making an optimal use of the capabilities of CW post-accelerators of the future facilities. Such a debunching technique should eventually resolve duty cycle and time structure issues which presently complicate the data-acquisition of experiments. The results of the first tests of this technique are reported here. In comparison with charge breeding with an EBIS, the ECRIS technique had lower performance in efficiency and attainable charge state for metallic ion beams and also suffered from issues related to beam contamination. In recent years, improvements have been made which significantly reduce the differences between the two techniques, making ECRIS charge breeding more attractive especially for CW machines producing intense beams. Upgraded versions of the Phoenix charge breeder, originally developed by LPSC, will be used at SPES and GANIL/SPIRAL. These two charge breeders have benefited from studies undertaken within EMILIE, which are also briefly summarized here.

  17. 105-K Basin Material Design Basis Feed Description for Spent Nuclear Fuel (SNF) Project Facilities VOL 1 Fuel

    SciTech Connect

    PACKER, M.J.

    1999-11-04

    Metallic uranium Spent Nuclear Fuel (SNF) is currently stored within two water filled pools, 105-KE Basin (KE Basin) and 105-KW Basin (KW Basin), at the United States Department of Energy (U.S. DOE) Hanford Site, in southeastern Washington State. The Spent Nuclear Fuel Project (SNF Project) is responsible to DOE for operation of these fuel storage pools and for the 2100 metric tons of SNF materials that they contain. The SNF Project mission includes safe removal and transportation of all SNF from these storage basins to a new storage facility in the 200 East Area. To accomplish this mission, the SNF Project modifies the existing KE Basin and KW Basin facilities and constructs two new facilities: the 100 K Area Cold Vacuum Drying Facility (CVDF), which drains and dries the SNF; and the 200 East Area Canister Storage Building (CSB), which stores the SNF. The purpose of this document is to describe the design basis feed compositions for materials stored or processed by SNF Project facilities and activities. This document is not intended to replace the Hanford Spent Fuel Inventory Baseline (WHC 1994b), but only to supplement it by providing more detail on the chemical and radiological inventories in the fuel (this volume) and sludge. A variety of feed definitions is required to support evaluation of specific facility and process considerations during the development of these new facilities. Six separate feed types have been identified for development of new storage or processing facilities. The approach for using each feed during design evaluations is to calculate the proposed facility flowsheet assuming each feed. The process flowsheet would then provide a basis for material compositions and quantities which are used in follow-on calculations.

  18. 7 CFR Appendix D to Subpart E of... - Alcohol Production Facilities Planning, Performing, Development and Project Control

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ..., Development and Project Control D Appendix D to Subpart E of Part 1980 Agriculture Regulations of the... (CONTINUED) GENERAL Business and Industrial Loan Program Pt. 1980, Subpt. E, App. D Appendix D to Subpart E... facilities and their relative operation and maintenance costs. (d) The project engineer or...

  19. 7 CFR Appendix D to Subpart E of... - Alcohol Production Facilities Planning, Performing, Development and Project Control

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ..., Development and Project Control D Appendix D to Subpart E of Part 1980 Agriculture Regulations of the... (CONTINUED) GENERAL Business and Industrial Loan Program Pt. 1980, Subpt. E, App. D Appendix D to Subpart E... facilities and their relative operation and maintenance costs. (d) The project engineer or...

  20. Project for the development of the linac based NCT facility in University of Tsukuba.

    PubMed

    Kumada, H; Matsumura, A; Sakurai, H; Sakae, T; Yoshioka, M; Kobayashi, H; Matsumoto, H; Kiyanagi, Y; Shibata, T; Nakashima, H

    2014-06-01

    A project team headed by University of Tsukuba launched the development of a new accelerator based BNCT facility. In the project, we have adopted Radio-Frequency Quadrupole (RFQ)+Drift Tube Linac (DTL) type linac as proton accelerators. Proton energy generated from the linac was set to 8MeV and average current was 10mA. The linac tube has been constructed by Mitsubishi Heavy Industry Co. For neutron generator device, beryllium is selected as neutron target material; high intensity neutrons are generated by the reaction with beryllium and the 80kW proton beam. Our team chose beryllium as the neutron target material. At present beryllium target system is being designed with Monte-Carlo estimations and heat analysis with ANSYS. The neutron generator consists of moderator, collimator and shielding. It is being designed together with the beryllium target system. We also acquired a building in Tokai village; the building has been renovated for use as BNCT treatment facility. It is noteworthy that the linac tube had been installed in the facility in September 2012. In BNCT procedure, several medical devices are required for BNCT treatment such as treatment planning system, patient positioning device and radiation monitors. Thus these are being developed together with the linac based neutron source. For treatment planning system, we are now developing a new multi-modal Monte-Carlo treatment planning system based on JCDS. The system allows us to perform dose estimation for BNCT as well as particle radiotherapy and X-ray therapy. And the patient positioning device can navigate a patient to irradiation position quickly and properly. Furthermore the device is able to monitor movement of the patient׳s position during irradiation. PMID:24637084

  1. HAZWOPER project documents for demolition of the Waste Evaporator Facility, Building 3506, at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1996-03-01

    This document, in support of the Waste Evaporator Facility (WEF) demolition project and contains the Project Work Plan and the Project Health and Safety Plan for demolition and partial remediation actions by ATG at the Waste Evaporator Facility, Building 3506. Various activities will be conducted during the course of demolition, and this plan provides details on the work steps involved, the identification of hazards, and the health and safety practices necessary to mitigate these hazards. The objective of this document is to develop an approach for implementing demolition activities at the WEF. This approach is based on prior site characterization information and takes into account all of the known hazards at this facility. The Project Work Plan provides instructions and requirements for identified work steps that will be utilized during the performance of demolition, while the Health and Safety Plan addresses the radiological, hazardous material exposure, and industrial safety concerns that will be encountered.

  2. Deactivation and Decommissioning Planning and Analysis with Geographic Information Systems

    SciTech Connect

    Bollinger, James S.; Koffman, Larry D.; Austin, William E.

    2008-01-15

    From the mid-1950's through the 1980's, the U.S. Department of Energy's Savannah River Site produced nuclear materials for the weapons stockpile, for medical and industrial applications, and for space exploration. Although SRS has a continuing defense-related mission, the overall site mission is now oriented toward environmental restoration and management of legacy chemical and nuclear waste. With the change in mission, SRS no longer has a need for much of the infrastructure developed to support the weapons program. This excess infrastructure, which includes over 1000 facilities, will be decommissioned and demolished over the forthcoming years. Dis-positioning facilities for decommissioning and deactivation requires significant resources to determine hazards, structure type, and a rough-order-of-magnitude estimate for the decommissioning and demolition cost. Geographic information systems (GIS) technology was used to help manage the process of dis-positioning infrastructure and for reporting the future status of impacted facilities. Several thousand facilities of various ages and conditions are present at SRS. Many of these facilities, built to support previous defense-related missions, now represent a potential hazard and cost for maintenance and surveillance. To reduce costs and the hazards associated with this excess infrastructure, SRS has developed an ambitious plan to decommission and demolish unneeded facilities in a systematic fashion. GIS technology was used to assist development of this plan by: providing locational information for remote facilities, identifying the location of known waste units adjacent to buildings slated for demolition, and for providing a powerful visual representation of the impact of the overall plan. Several steps were required for the development of the infrastructure GIS model. The first step involved creating an accurate and current GIS representation of the infrastructure data. This data is maintained in a Computer Aided Design

  3. Sludge treatment facility preliminary siting study for the sludge treatment project (A-13B)

    SciTech Connect

    WESTRA, A.G.

    1999-06-24

    This study evaluates various sites in the 100 K area and 200 areas of Hanford for locating a treatment facility for sludge from the K Basins. Both existing facilities and a new standalone facility were evaluated. A standalone facility adjacent to the AW Tank Farm in the 200 East area of Hanford is recommended as the best location for a sludge treatment facility.

  4. Catalytic reforming of liquid fuels: Deactivation of catalysts

    SciTech Connect

    Spivey, J.J.; Haynes, D.J.; Berry, D.A.; Shekhawat, Dushyant; Gardner, T.H.

    2007-10-01

    The catalytic reforming of logistic fuels (e.g., diesel) to provide hydrogen-rich gas for various fuel cells is inevitably accompanied by deactivation. This deactivation can be caused by various mechanisms, such as carbon deposition, sintering, and sulfur poisoning. In general, these mechanisms are, not independent—e.g., carbon deposition may affect sulfur poisoning. However, they are typically studied in separate experiments, with relatively little work reported on their interaction at conditions typical of liquid fuel reforming. Recent work at the U.S. Dept. of Energy/NETL and Louisiana State University has shown progress in understanding the interaction of these deactivation processes, and catalysts designed to minimize them.

  5. Complementary and Integrative Healthcare in a Long-term Care Facility: A Pilot Project

    PubMed Central

    Vihstadt, Corrie; Westrom, Kristine; Baldwin, Lori

    2015-01-01

    Introduction: The world's population is aging quickly, leading to increased challenges of how to care for individuals who can no longer independently care for themselves. With global social and economic pressures leading to declines in family support, increased reliance is being placed on community- and government-based facilities to provide long-term care (LTC) for many of society's older citizens. Complementary and integrative healthcare (CIH) is commonly used by older adults and may offer an opportunity to enhance LTC residents' wellbeing. Little work has been done, however, rigorously examining the safety and effectiveness of CIH for LTC residents. Objective: The goal of this work is to describe a pilot project to develop and evaluate one model of CIH in an LTC facility in the Midwestern United States. Methods: A prospective, mixed-methods pilot project was conducted in two main phases: (1) preparation and (2) implementation and evaluation. The preparation phase entailed assessment, CIH model design and development, and training. A CIH model including acupuncture, chiropractic, and massage therapy, guided by principles of collaborative integration, evidence informed practice, and sustainability, was applied in the implementation and evaluation phase. CIH services were provided for 16 months in the LTC facility. Quantitative data collection included pain, quality of life, and adverse events. Qualitative interviews of LTC residents, their family members, and LTC staff members queried perceptions of CIH services. Results: A total of 46 LTC residents received CIH care, most commonly for musculoskeletal pain (61%). Participants were predominantly female (85%) and over the age of 80 years (67%). The median number of CIH treatments was 13, with a range of 1 to 92. Residents who were able to provide self-report data demonstrated, on average, a 15% decline in pain and a 4% improvement in quality of life. No serious adverse events related to treatment were documented

  6. Hot Corrosion Test Facility at the NASA Lewis Special Projects Laboratory

    NASA Technical Reports Server (NTRS)

    Robinson, Raymond C.; Cuy, Michael D.

    1994-01-01

    The Hot Corrosion Test Facility (HCTF) at the NASA Lewis Special Projects Laboratory (SPL) is a high-velocity, pressurized burner rig currently used to evaluate the environmental durability of advanced ceramic materials such as SiC and Si3N4. The HCTF uses laboratory service air which is preheated, mixed with jet fuel, and ignited to simulate the conditions of a gas turbine engine. Air, fuel, and water systems are computer-controlled to maintain test conditions which include maximum air flows of 250 kg/hr (550 lbm/hr), pressures of 100-600 kPa (1-6 atm), and gas temperatures exceeding 1500 C (2732 F). The HCTF provides a relatively inexpensive, yet sophisticated means for researchers to study the high-temperature oxidation of advanced materials, and the injection of a salt solution provides the added capability of conducting hot corrosion studies.

  7. Commercial Light Water Reactor -Tritium Extraction Facility Process Waste Assessment (Project S-6091)

    SciTech Connect

    Hsu, R.H.; Delley, A.O.; Alexander, G.J.; Clark, E.A.; Holder, J.S.; Lutz, R.N.; Malstrom, R.A.; Nobles, B.R.; Carson, S.D.; Peterson, P.K.

    1997-11-30

    The Savannah River Site (SRS) has been tasked by the Department of Energy (DOE) to design and construct a Tritium Extraction Facility (TEF) to process irradiated tritium producing burnable absorber rods (TPBARs) from a Commercial Light Water Reactor (CLWR). The plan is for the CLWR-TEF to provide tritium to the SRS Replacement Tritium Facility (RTF) in Building 233-H in support of DOE requirements. The CLWR-TEF is being designed to provide 3 kg of new tritium per year, from TPBARS and other sources of tritium (Ref. 1-4).The CLWR TPBAR concept is being developed by Pacific Northwest National Laboratory (PNNL). The TPBAR assemblies will be irradiated in a Commercial Utility light water nuclear reactor and transported to the SRS for tritium extraction and processing at the CLWR-TEF. A Conceptual Design Report for the CLWR-TEF Project was issued in July 1997 (Ref. 4).The scope of this Process Waste Assessment (PWA) will be limited to CLWR-TEF processing of CLWR irradiated TPBARs. Although the CLWR- TEF will also be designed to extract APT tritium-containing materials, they will be excluded at this time to facilitate timely development of this PWA. As with any process, CLWR-TEF waste stream characteristics will depend on process feedstock and contaminant sources. If irradiated APT tritium-containing materials are to be processed in the CLWR-TEF, this PWA should be revised to reflect the introduction of this contaminant source term.

  8. Spent nuclear fuel project, Cold Vacuum Drying Facility human factors engineering (HFE) analysis: Results and findings

    SciTech Connect

    Garvin, L.J.

    1998-07-17

    This report presents the background, methodology, and findings of a human factors engineering (HFE) analysis performed in May, 1998, of the Spent Nuclear Fuels (SNF) Project Cold Vacuum Drying Facility (CVDF), to support its Preliminary Safety Analysis Report (PSAR), in responding to the requirements of Department of Energy (DOE) Order 5480.23 (DOE 1992a) and drafted to DOE-STD-3009-94 format. This HFE analysis focused on general environment, physical and computer workstations, and handling devices involved in or directly supporting the technical operations of the facility. This report makes no attempt to interpret or evaluate the safety significance of the HFE analysis findings. The HFE findings presented in this report, along with the results of the CVDF PSAR Chapter 3, Hazards and Accident Analyses, provide the technical basis for preparing the CVDF PSAR Chapter 13, Human Factors Engineering, including interpretation and disposition of findings. The findings presented in this report allow the PSAR Chapter 13 to fully respond to HFE requirements established in DOE Order 5480.23. DOE 5480.23, Nuclear Safety Analysis Reports, Section 8b(3)(n) and Attachment 1, Section-M, require that HFE be analyzed in the PSAR for the adequacy of the current design and planned construction for internal and external communications, operational aids, instrumentation and controls, environmental factors such as heat, light, and noise and that an assessment of human performance under abnormal and emergency conditions be performed (DOE 1992a).

  9. EERC pilot-scale CFBC evaluation facility Project CFB test results

    SciTech Connect

    Mann, M.D.; Hajicek, D.R.; Henderson, A.K.; Moe, T.A.

    1992-09-01

    Project CFB was initiated at the University of North Dakota Energy and Environmental Research Center (EERC) in May 1988. Specific goals of the project were to (1) construct a circulating fluidized-bed combustor (CFBC) facility representative of the major boiler vendors' designs with the capability of producing scalable data, (2) develop a database for use in making future evaluations of CFBC technology, and (3) provide a facility for evaluating fuels, free of vendor bias for use in the - energy industry. Five coals were test-burned in the 1-MWth unit: North Dakota and Asian lignites, a Wyoming subbituminous, and Colorado and Pennsylvania bituminous coats. A total of 54 steady-state test periods were conducted, with the key test parameters being the average combustor temperature, excess air, superficial gas velocity, calcium-to-sulfur molar ratio, and the primary air-to-secondary air split. The capture for a coal fired in a CFBC is primarily dependent upon the total alkali-to-sulfur ratio. The required alkali-to ratio for 90% sulfur retention ranged from 1.4 to 4.9, depending upon coal type. While an alkali-to-ratio of 4.9 was required to meet 90% sulfur retention for the Salt Creek coal versus 1.4 for the Asian lignite, the total amount of sorbent addition required is much less for the Salt Creek coal, 4.2 pound sorbent per million Btu coal input, versus 62 pound/million Btu for the Asian lignite. The bituminous coals tested show optimal capture at combustor temperatures of approximately 1550[degree]F, with low-rank coals having optimal sulfur capture approximately 100[degree]F lower.

  10. Deactivation of snares by wild chimpanzees.

    PubMed

    Ohashi, Gaku; Matsuzawa, Tetsuro

    2011-01-01

    Snare injuries to chimpanzees (Pan troglodytes) have been reported at many study sites across Africa, and in some cases cause the death of the ensnared animal. However, very few snare injuries have been reported concerning the chimpanzees of Bossou, Guinea. The rarity of snare injuries in this study group warrants further consideration, given the exceptionally close proximity of the Bossou chimpanzees to human settlements and the widespread practice of snare hunting in the area. Herein we report a total of six observations of chimpanzees attempting to break and deactivate snares, successfully doing so on two of these occasions. We observed the behavior in 5 males, ranging in age from juveniles to adults. We argue that such active responses to snares must be contributing to the rarity of injuries in this group. Based on our observations, we suggest that the behavior has transmitted down the group. Our research team at Bossou continues to remove snares from the forest, but the threat of ensnarement still remains. We discuss potential ways to achieve a good balance between human subsistence activities and the conservation of chimpanzees at Bossou, which will increasingly be an area of great concern in the future. PMID:20700626

  11. Lens hexokinase deactivation by near-UV irradiation.

    PubMed

    Tung, W H; Chylack, L T; Andley, U P

    1988-03-01

    Photodamage to lens hexokinase has been investigated by exposing the lenses of rat, rabbit and calf eyes to 300 nm irradiation. Hexokinase activity was diminished by 15.9% +/- 5.4 and 23.4% +/- 5.0 upon irradiation of the isolated rat lens for 1 and 2 hours respectively. Irradiation of the whole eye for 2 hours resulted in hexokinase deactivation of 13.6% +/- 5.8 and 19.2% +/- 6.2 for rat and rabbit lens homogenates and 55% +/- 7 for calf lens capsule plus epithelium. Enzyme deactivation was prevented when the isolated lens was irradiated with the vitreous attached. Glucose, catalase or ascorbate added to the medium prior to irradiation, each had a protective effect on hexokinase deactivation. The results are consistent with a mechanism in which photochemical generation of active species of oxygen, via the photosensitizing action of tryptophan photoproducts, plays a significant role in enzyme deactivation. PMID:3359812

  12. Deactivation of Pacemakers and Implantable Cardioverter-Defibrillators

    PubMed Central

    Kramer, Daniel B.; Mitchell, Susan L.; Brock, Dan W.

    2013-01-01

    Cardiac implantable electrical devices (CIEDs), including pacemakers (PMs) and implantable cardioverter-defibrillators (ICDs), are the most effective treatment for life-threatening arrhythmias. Patients or their surrogates may request device deactivation to avoid prolongation of the dying process or in other settings, such as after device-related complications or with changes in their health care goals. Despite published guidelines outlining theoretical and practical aspects of this common clinical scenario, significant uncertainty remains for both patients and health care providers regarding the ethical and legal status of CIED deactivation. This review outlines the ethical and legal principles supporting CIED deactivation at patients’ request, centered upon patient autonomy and authority over their own medical treatment. The empirical literature describing stakeholder views and experiences surrounding CIED deactivation is described, along with lessons for future research and practice guidance surrounding the care of patients with CIEDs. PMID:23217433

  13. The effect of sorbitol on acid phosphatase deactivation.

    PubMed

    Gianfreda, L; Toscano, G; Pirozzi, D; Greco, G

    1991-12-01

    Acid phosphatase thermal deactivation follows a complex path: an initial decay toward an equilibrium distribution of at least two intermediate structures, mutually at the equilibrium, followed by a final breakdown toward a completely inactive enzyme configuration. The results obtained in the presence of sorbitol have been compared to those produced in the course of purely thermal deactivation of the native enzyme. For any sobitol concentration, an equivalent temperature is calculated that results in exactly the same activity-versus-time profile. This suggests enzyme deactivation to be controlled by a single, unchanging step. Immobilized enzyme runs have been performed, as well, by entrapping acid phosphates within a polymeric network formed onto the upstream surface of an ultrafiltration membrane. The stabilizing effect of entrapment cumulates with that produced by sorbitol. In this case, however, an equivalent temperature cannot be determined, thus indicating that a different deactivation mechanism is followed. PMID:18600710

  14. Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

    SciTech Connect

    IRWIN, J.J.

    2000-11-18

    The mission of the Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying Facility (CVDF) is to achieve the earliest possible removal of free water from Multi-Canister Overpacks (MCOs). The MCOs contain metallic uranium SNF that have been removed from the 100K Area fuel storage water basins (i.e., the K East and K West Basins) at the US. Department of Energy Hanford Site in Southeastern Washington state. Removal of free water is necessary to halt water-induced corrosion of exposed uranium surfaces and to allow the MCOs and their SNF payloads to be safely transported to the Hanford Site 200 East Area and stored within the SNF Project Canister Storage Building (CSB). The CVDF is located within a few hundred yards of the basins, southwest of the 165KW Power Control Building and the 105KW Reactor Building. The site area required for the facility and vehicle circulation is approximately 2 acres. Access and egress is provided by the main entrance to the 100K inner area using existing roadways. The CVDF will remove free. water from the MCOs to reduce the potential for continued fuel-water corrosion reactions. The cold vacuum drying process involves the draining of bulk water from the MCO and subsequent vacuum drying. The MCO will be evacuated to a pressure of 8 torr or less and backfilled with an inert gas (helium). The MCO will be sealed, leak tested, and then transported to the CSB within a sealed shipping cask. (The MCO remains within the same shipping Cask from the time it enters the basin to receive its SNF payload until it is removed from the Cask by the CSB MCO handling machine.) The CVDF subproject acquired the required process systems, supporting equipment, and facilities. The cold vacuum drying operations result in an MCO containing dried fuel that is prepared for shipment to the CSB by the Cask transportation system. The CVDF subproject also provides equipment to dispose of solid wastes generated by the cold vacuum drying process and transfer process water removed

  15. Decontamination and dismantlement of the building 594 waste ion exchange facility at Argonne National Laboratory-East project final report.

    SciTech Connect

    Wiese, E. C.

    1998-11-23

    The Building 594 D&D Project was directed toward the following goals: Removal of any radioactive and hazardous materials associated with the Waste Ion Exchange Facility; Decontamination of the Waste Ion Exchange Facility to unrestricted use levels; Demolition of Building 594; and Documentation of all project activities affecting quality (i.e., waste packaging, instrument calibration, audit results, and personnel exposure) These goals had been set in order to eliminate the radiological and hazardous safety concerns inherent in the Waste Ion Exchange Facility and to allow, upon completion of the project, unescorted and unmonitored access to the area. The ion exchange system and the resin contained in the system were the primary areas of concern, while the condition of the building which housed the system was of secondary concern. ANL-E health physics technicians characterized the Building 594 Waste Ion Exchange Facility in September 1996. The characterization identified a total of three radionuclides present in the Waste Ion Exchange Facility with a total activity of less than 5 {micro}Ci (175 kBq). The radionuclides of concern were Co{sup 60}, Cs{sup 137}, and Am{sup 241}. The highest dose rates observed during the project were associated with the resin in the exchange vessels. DOE Order 5480.2A establishes the maximum whole body exposure for occupational workers at 5 rem (50 mSv)/yr; the administrative limit at ANL-E is 1 rem/yr (10 mSv/yr).

  16. Design of the Long-term Waste Management Facility for Historic LLRW Port Hope Project - 13322

    SciTech Connect

    Campbell, Don; Barton, David; Case, Glenn

    2013-07-01

    The Municipality of Port Hope is located on the northern shores of Lake Ontario approximately 100 km east of Toronto, Ontario, Canada. Starting in the 1930's, radium and later uranium processing by Eldorado Gold Mines Limited (subsequently Eldorado Nuclear Limited) (Eldorado) at their refinery in Port Hope resulted in the generation of process residues and wastes that were disposed of indiscriminately throughout the Municipality until about the mid-1950's. These process residues contained radium (Ra- 226), uranium, arsenic and other contaminants. Between 1944 and 1988, Eldorado was a Federal Crown Corporation, and as such, the Canadian Federal Government has assumed responsibility for the clean-up and long-term management of the historic waste produced by Eldorado during this period. The Port Hope Project involves the construction and development of a new long-term waste management facility (LTWMF), and the remediation and transfer of the historic wastes located within the Municipality of Port Hope to the new LTWMF. The new LTWMF will consist of an engineered above-ground containment mound designed to contain and isolate the wastes from the surrounding environment for the next several hundred years. The design of the engineered containment mound consists of a primary and secondary composite base liner system and composite final cover system, made up of both natural materials (e.g., compacted clay, granular materials) and synthetic materials (e.g., geo-synthetic clay liner, geo-membrane, geo-textiles). The engineered containment mound will cover an area of approximately 13 hectares and will contain the estimated 1.2 million cubic metres of waste that will be generated from the remedial activities within Port Hope. The LTWMF will also include infrastructure and support facilities such as access roads, administrative offices, laboratory, equipment and personnel decontamination facilities, waste water treatment plant and other ancillary facilities. Preliminary

  17. The Los Alamos National Laboratory Chemistry and Metallurgy Research Facility upgrades project - A model for waste minimization

    SciTech Connect

    Burns, M.L.; Durrer, R.E.; Kennicott, M.A.

    1996-07-01

    The Los Alamos National Laboratory (LANL) Chemistry and Metallurgy Research (CMR) Facility, constructed in 1952, is currently undergoing a major, multi-year construction project. Many of the operations required under this project (i.e., design, demolition, decontamination, construction, and waste management) mimic the processes required of a large scale decontamination and decommissioning (D&D) job and are identical to the requirements of any of several upgrades projects anticipated for LANL and other Department of Energy (DOE) sites. For these reasons the CMR Upgrades Project is seen as an ideal model facility - to test the application, and measure the success of - waste minimization techniques which could be brought to bear on any of the similar projects. The purpose of this paper will be to discuss the past, present, and anticipated waste minimization applications at the facility and will focus on the development and execution of the project`s {open_quotes}Waste Minimization/Pollution Prevention Strategic Plan.{close_quotes}

  18. Copper Cable Recycling System - The INEEL LSDDP Demonstration Project

    SciTech Connect

    Conner, Craig C; Meservey, Richard Harlan; Rosenberger, S.

    2001-02-01

    The United States Department of Energy (DOE) continually seeks safer and more cost-effective technologies for the deactivation and decommissioning (D&D) of nuclear facilities. The Deactivation and Decommissioning Focus Area (DDFA) and the DOE’s office of Science and Technology (OST) sponsors Large Scale Demonstration and Deployment Projects (LSDDPs). The increasing number of deactivation and decommissioning (D&D) activities at nuclear facilities can generate hundreds of tons of cables per facility consuming valuable resources such as disposal space and copper. Driven by increasing environmental concerns as well as economical pressures there is a developing need for the recycling of the uncontaminated copper. As part of the LSDDP program the NUKEM Copper Cable Recycling System (CCRS) was demonstrated November 1999 at the Idaho National Engineering and Environmental Laboratory (INEEL). This process allows recovering and recycling the uncontaminated copper contained in surface contaminated cables. The NUKEM CCRS was originally developed in Germany for the use during the D&D of commercial power plants. Up to date the CCRS has successfully processed in Germany more than 200 metric tons of contaminated cables resulting in virtually 100% free release of copper under the German standards. A total of 13.5 tons non and surrogate contaminated cables in a wide variety of sizes were successfully processed during the technology demonstration at INEEL. The assessment has demonstrated the mobility and flexibility of this new process.

  19. Dismantlement and decontamination of a plutonium-238 facility at SRS

    SciTech Connect

    Smith, R.H. Jr.; Hootman, H.E.

    1994-01-01

    There has been very little, documented decontamination and decommissioning (D&D) experience on which to project cleanup costs and schedules for plutonium facilities at SRS and other DOE sites. A portion of the HB-Line, a plutonium-238 processing facility at SRS, has been undergoing D&D intermittently since 1984. Although this cleanup effort was not originally intended to quantify results, some key data have been project has demonstrated effective methods of accumulated, and the performing D&D work, and has demonstrated cleanup equipment and techniques under conditions of high contamination. Plutonium facilities where D&D is already underway provide an opportunity for` timely field testing of characterization, size reduction, and decontamination techniques. Some data are presented here; however, more specific tests and data may be obtained during the remainder of this project. This project has been recommended as a candidate test facility for a DOE planned ``Integrated D&D Demonstration`` managed by EM-50 to develop and demonstrate technology for D&D and surplus facilities deactivation. Both the remainder of this project and the Integrated D&D Demonstration Program can benefit from a joint effort, and the, overall costs should be reduced.

  20. Report of the ANS Project Feasibility Workshop for a High Flux Isotope Reactor-Center for Neutron Research Facility

    SciTech Connect

    Peretz, F.J.; Booth, R.S.

    1995-07-01

    The Advanced Neutron Source (ANS) Conceptual Design Report (CDR) and its subsequent updates provided definitive design, cost, and schedule estimates for the entire ANS Project. A recent update to this estimate of the total project cost for this facility was $2.9 billion, as specified in the FY 1996 Congressional data sheet, reflecting a line-item start in FY 1995. In December 1994, ANS management decided to prepare a significantly lower-cost option for a research facility based on ANS which could be considered during FY 1997 budget deliberations if DOE or Congressional planners wished. A cost reduction for ANS of about $1 billion was desired for this new option. It was decided that such a cost reduction could be achieved only by a significant reduction in the ANS research scope and by maximum, cost-effective use of existing High Flux Isotope Reactor (HFIR) and ORNL facilities to minimize the need for new buildings. However, two central missions of the ANS -- neutron scattering research and isotope production-were to be retained. The title selected for this new option was High Flux Isotope Reactor-Center for Neutron Research (HFIR-CNR) because of the project`s maximum use of existing HFIR facilities and retention of selected, central ANS missions. Assuming this shared-facility requirement would necessitate construction work near HFIR, it was specified that HFIR-CNR construction should not disrupt normal operation of HFIR. Additional objectives of the study were that it be highly credible and that any material that might be needed for US Department of Energy (DOE) and Congressional deliberations be produced quickly using minimum project resources. This requirement made it necessary to rely heavily on the ANS design, cost, and schedule baselines. A workshop methodology was selected because assessment of each cost and/or scope-reduction idea required nearly continuous communication among project personnel to ensure that all ramifications of propsed changes.

  1. Final report of the decontamination and decommissioning of the exterior land areas at the Grand Junction Projects Office facility

    SciTech Connect

    Widdop, M.R.

    1995-09-01

    The US Department of Energy (DOE) Grand Junction Projects Office (GJPO) facility occupies approximately 56.4 acres (22.8 hectares) along the Gunnison River near Grand Junction, Colorado. The site was contaminated with uranium ore and mill tailings during uranium-refining activities conducted by the Manhattan Engineer District and during pilot-milling experiments conducted for the US Atomic Energy Commission`s (AEC`s) domestic uranium procurement program. The GJPO facility was the collection and assay point for AEC uranium and vanadium oxide purchases until the early 1970s. The DOE Decontamination and Decommissioning Program sponsored the Grand Junction Projects Office Remedial Action Project (GJPORAP) to remediate the facility lands, site improvements, and the underlying aquifer. The site contractor, Rust Geotech, was the Remedial Action Contractor for GJPORAP. The exterior land areas of the facility assessed as contaminated have been remediated in accordance with identified standards and can be released for unrestricted use. Restoration of the aquifer will be accomplished through the natural flushing action of the aquifer during the next 50 to 80 years. The remediation of the DOE-GJPO facility buildings is ongoing and will be described in a separate report.

  2. DEACTIVATION AND DECOMMISSIONING (D AND D) TECHNOLOGY INTEGRATION

    SciTech Connect

    M.A. Ebadian, Ph.D.

    1999-01-01

    As part of the ongoing task of making Deactivation and Decommissioning (D&D) operations more efficient, this subtask has addressed the need to integrate existing characterization technologies with decontamination technologies in order to provide real-time data on the progress of contamination removal. Specifically, technologies associated with concrete decontamination and/or removal have been examined with the goal of integrating existing technologies and commercializing the resulting hybrid. The Department of Energy (DOE) has estimated that 23 million cubic meters of concrete will require disposition as 1200 buildings undergo the D&D process. All concrete removal to be performed will also necessitate extensive use of characterization techniques. The in-process characterization presents the most potential for improvement and cost-savings as compared to other types. Current methods for in-process characterization usually require cessation of work to allow for radiation surveys to assess the rate of decontamination. Combining together decontamination and characterization technologies would allow for in-process evaluation of decontamination efforts. Since the present methods do not use in-process evaluations for the progress of decontamination, they may allow for ''overremoval'' of materials (removal of contaminated along with non-contaminated materials). Overremoval increases the volume of waste and therefore the costs associated with disposal. Integrating technologies would facilitate the removal of only contaminated concrete and reduce the total volume of radioactive waste, which would be disposed of. This would eventually ensure better productivity and time savings. This project presents a general procedure to integrate the above-mentioned technologies in the form of the Technology Integration Module (TIM) along with combination lists of commercially available decontamination and characterization technologies. The scope of the project has also been expanded by FIU

  3. A student-led demonstration project on fall prevention in a long-term care facility.

    PubMed

    Bonner, Alice; MacCulloch, Patricia; Gardner, Terri; Chase, Chantel W

    2007-01-01

    .1%; 30-day posttraining fall rate was 12.3%, and 60-day postintervention fall rate was 9%. Based on the program results, the model was expanded from long-term care to the university hospital system and outpatient clinics in the same community. The collaboration between a school of nursing and 1 long-term care facility led to the adoption of a significant quality improvement program that was subsequently extended to a local hospital and clinic system. Student-led projects designed to teach community service learning can be meaningful and can lead to changes in patient safety and quality of care. PMID:17923288

  4. Prognostic Value of Posteromedial Cortex Deactivation in Mild Cognitive Impairment

    PubMed Central

    Petrella, Jeffrey R.; Prince, Steven E.; Wang, Lihong; Hellegers, Caroline; Doraiswamy, P. Murali

    2007-01-01

    Background Normal subjects deactivate specific brain regions, notably the posteromedial cortex (PMC), during many tasks. Recent cross-sectional functional magnetic resonance imaging (fMRI) data suggests that deactivation during memory tasks is impaired in Alzheimer's disease (AD). The goal of this study was to prospectively determine the prognostic significance of PMC deactivation in mild cognitive impairment (MCI). Methodology/Principal Findings 75 subjects (34 MCI, 13 AD subjects and 28 controls) underwent baseline fMRI scanning during encoding of novel and familiar face-name pairs. MCI subjects were followed longitudinally to determine conversion to AD. Regression and analysis of covariance models were used to assess the effect of PMC activation/deactivation on conversion to dementia as well as in the longitudinal change in dementia measures. At longitudinal follow up of up to 3.5 years (mean 2.5±0.79 years), 11 MCI subjects converted to AD. The proportion of deactivators was significantly different across all groups: controls (79%), MCI-Nonconverters (73%), MCI-converters (45%), and AD (23%) (p<0.05). Mean PMC activation magnitude parameter estimates, at baseline, were negative in the control (−0.57±0.12) and MCI-Nonconverter (−0.33±0.14) groups, and positive in the MCI-Converter (0.37±0.40) and AD (0.92±0.30) groups. The effect of diagnosis on PMC deactivation remained significant after adjusting for age, education and baseline Mini-Mental State Exam (p<0.05). Baseline PMC activation magnitude was correlated with change in dementia ratings from baseline. Conclusion Loss of physiological functional deactivation in the PMC may have prognostic value in preclinical AD, and could aid in profiling subgroups of MCI subjects at greatest risk for progressive cognitive decline. PMID:17971867

  5. 77 FR 32621 - Developing Large-Scale Renewable Energy Projects at Federal Facilities Using Private Capital Draft

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-06-01

    ... of Energy Efficiency and Renewable Energy Developing Large-Scale Renewable Energy Projects at Federal Facilities Using Private Capital Draft AGENCY: Office of Energy Efficiency and Renewable Energy, Department... draft guidebook entitled Federal Renewable Energy Guide: Developing Large-Scale Renewable...

  6. 7 CFR Appendix D to Subpart E of... - Alcohol Production Facilities Planning, Performing, Development and Project Control

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 7 Agriculture 14 2010-01-01 2009-01-01 true Alcohol Production Facilities Planning, Performing, Development and Project Control D Appendix D to Subpart E of Part 1980 Agriculture Regulations of the Department of Agriculture (Continued) RURAL HOUSING SERVICE, RURAL BUSINESS-COOPERATIVE SERVICE, RURAL UTILITIES SERVICE, AND FARM SERVICE...

  7. Interim reclamation report, Basalt Waste Isolation Project Near Surface Test Facility 1990

    SciTech Connect

    Brandt, C.A.; Rickard, W.H. Jr.; Hefty, M.G.; Cadoret, N.A.

    1991-01-01

    This report describes the development of the reclamation project for the Hanford Site Near Surface Test Facility (NSTF), its implementation, and preliminary estimates of its success. The goal of the reclamation project is to return disturbed sites as nearly as practicable to their original conditions using native species. Gable Mountain is dominated by two plant communities: a big sagebrush (Artemisia tridentata) -- Sandberg's bluegrass (Poa sandbergii) community and a stiff sagebrush (Artemisia rigida) -- Sandberg's bluegrass community. Disassembly of the site installations began on March 15, 1988, and the site was returned to original contours by December 12, 1988. Two separate revegetation methods were employed at the NSTF to meet differing site constraints. Vegetative cover and density in the revegetation plots were assessed in April 1989 and again in June 1989 and 1990. It is extremely unlikely that the sand pit, borrow pit, box cuts, generator pad area, or ventilation fan area will reach the reclamation objectives set for these areas within the next 50 years without further intervention. These areas currently support few living plants. Vegetation on revegetated native soils appears to be growing as expected. Vegetation growth on the main waterline is well below the objective. To date, no shrubs have grown on the area, growth of native grasses is well below the objective, and much of the area has been covered with the pit run material, which may not support adequate growth. Without further treatments, the areas without the pit run material will likely revert to a nearly pure cheatgrass condition. 44 refs., 13 figs., 7 tabs.

  8. Hot gas cleanup test facility for gasification and pressurized combustion project. Quarterly report, October--December 1995

    SciTech Connect

    1996-02-01

    The objective of this project is to evaluate hot gas particle control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the original Transport Reactor gas source and Hot Gas Cleanup Units: Carbonizer/pressurized circulating fluidized bed gas source; hot gas cleanup units to mate to all gas streams; combustion gas turbine; and fuel cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF). The major emphasis during this reporting period was continuing the detailed design of the facility towards completion and integrating the balance-of-plant processes and particulate control devices (PCDs) into the structural and process designs. Substantial progress in construction activities was achieved during this quarter.

  9. Sampling and analysis plan for the preoperational environmental survey of the spent nuclear fuel project facilities

    SciTech Connect

    MITCHELL, R.M.

    1999-04-01

    This sampling and analysis plan will support the preoperational environmental monitoring for construction, development, and operation of the Spent Nuclear Fuel (SNF) Project facilities, which have been designed for the conditioning and storage of spent nuclear fuels; particularly the fuel elements associated with the operation of N-Reactor. The SNF consists principally of irradiated metallic uranium, and therefore includes plutonium and mixed fission products. The primary effort will consist of removing the SNF from the storage basins in K East and K West Areas, placing in multicanister overpacks, vacuum drying, conditioning, and subsequent dry vault storage in the 200 East Area. The primary purpose and need for this action is to reduce the risks to public health and safety and to the environment. Specifically these include prevention of the release of radioactive materials into the air or to the soil surrounding the K Basins, prevention of the potential migration of radionuclides through the soil column to the nearby Columbia River, reduction of occupational radiation exposure, and elimination of the risks to the public and to workers from the deterioration of SNF in the K Basins.

  10. Fort Irwin integrated resource assessment. Volume 3: Sitewide Energy Project identification for buildings and facilities

    SciTech Connect

    Keller, J.M.; Dittmer, A.L.; Elliott, D.B.; McMordie, K.L.; Richman, E.E.; Stucky, D.J.; Wahlstrom, R.R.; Hadley, D.L.

    1995-02-01

    The U.S. Army Forces Command (FORSCOM) has tasked the U.S. Department of Energy (DOE) Federal Energy Management Program (FEMP), supported by the Pacific Northwest Laboratory, to identify, evaluate, and assist in acquiring all cost-effective energy projects at Fort Irwin. This is part of a model program that PNL is designing to support energy-use decisions in the federal sector. This report provides the results of the fossil fuel and electric energy resource opportunity (ERO) assessments performed by PNL at the FORSCOM Fort Irwin facility located near Barstow, California. It is a companion report to Volume 1, Executive Summary, and Volume 2, Baseline Detail. The results of the analyses of EROs are presented in 16 common energy end-use categories (e.g., boilers and furnaces, service hot water, and building lighting). A narrative description of each ERO is provided, along with a table detailing information on the installed cost, energy and dollar savings; impacts on operations and maintenance (O&M); and, when applicable, a discussion of energy supply and demand, energy security, and environmental issues. A description of the evaluation methodologies and technical and cost assumptions is also provided for each ERO. Summary tables present the cost-effectiveness of energy end-use equipment before and after the implementation of each ERO and present the results of the life-cycle cost (LCC) analysis indicating the net present valve (NPV) and savings-to-investment ratio (SIR) of each ERO.

  11. Dopaminergic Suppression of Brain Deactivation Responses during Sequence Learning

    PubMed Central

    Argyelan, Miklos; Carbon, Maren; Ghilardi, Maria-Felice; Feigin, Andrew; Mattis, Paul; Tang, Chengke; Dhawan, Vijay; Eidelberg, David

    2015-01-01

    Cognitive processing is associated with deactivation of the default mode network. The presence of dopaminoceptive neurons in proximity to the medial prefrontal node of this network suggests that this neurotransmitter may modulate deactivation in this region. We therefore used positron emission tomography to measure cerebral blood flow in 15 Parkinson's disease (PD) patients while they performed a motor sequence learning task and a simple movement task. Scanning was conducted before and during intravenous levodopa infusion; the pace and extent of movement was controlled across tasks and treatment conditions. In normal and unmedicated PD patients, learning-related deactivation was present in the ventromedial prefrontal cortex (p < 0.001). This response was absent in the treated condition. Treatment-mediated changes in deactivation correlated with baseline performance (p < 0.002) and with the val158met catechol-O-methyltransferase genotype. Our findings suggest that dopamine can influence prefrontal deactivation during learning, and that these changes are linked to baseline performance and genotype. PMID:18923044

  12. Diagnosis of industrial catalyst deactivation by surface characterization techniques

    SciTech Connect

    Menon, P.G. . Lab. voor Petrochemische Techniek Chalmers Univ. of Technology, Goeteborg . Dept. of Engineering Chemistry)

    1994-06-01

    The exact nature of the catalyst surface and the various ways of catalyst deactivation are subjects of great scientific interest and enormous economic importance. A brief review like the present one has to be very selective, giving only the underlying principles and representative examples. The focus of this review is on industrial catalysts, in particular, on the most commonly used supported metal and mixed-oxide type catalysts. Here again, only typical examples are chosen and cited to illustrate the specific types of problems involved in catalyst deactivation and how these problems wee diagnosed by a judicious application of the experimental techniques available today. Of the types of catalyst deactivation caused by coking, poisoning, and solid-state transformations, the emphasis in this review is on the last type. Changes in the chemical composition of the catalyst surface, restructuring or reconstruction of the surface, phase transformations, gradual enrichment/depletion of a particular catalyst component on/from the catalyst surface, these are the topics of prominence in this review. Even here, emphasis is on normally unexpected or unsuspected types of deactivation and the catalyst metamorphosis produced by the catalytic reaction itself, as distinct from the purely thermal effects at the reaction temperature. This review is aimed to provide some essential background information and possibly to serve as a reference guide for trouble-shooting when a catalyst is deactivated for rather mysterious reasons. 147 refs.

  13. SLUDGE TREATMENT PROJECT PHASE 1 SLUDGE STORAGE OPTIONS ASSESSMENT OF T PLANT VERSUS ALTERNATE STORAGE FACILITY

    SciTech Connect

    RUTHERFORD WW; GEUTHER WJ; STRANKMAN MR; CONRAD EA; RHOADARMER DD; BLACK DM; POTTMEYER JA

    2009-04-29

    The CH2M HILL Plateau Remediation Company (CHPRC) has recommended to the U.S. Department of Energy (DOE) a two phase approach for removal and storage (Phase 1) and treatment and packaging for offsite shipment (Phase 2) of the sludge currently stored within the 105-K West Basin. This two phased strategy enables early removal of sludge from the 105-K West Basin by 2015, allowing remediation of historical unplanned releases of waste and closure of the 100-K Area. In Phase 1, the sludge currently stored in the Engineered Containers and Settler Tanks within the 105-K West Basin will be transferred into sludge transport and storage containers (STSCs). The STSCs will be transported to an interim storage facility. In Phase 2, sludge will be processed (treated) to meet shipping and disposal requirements and the sludge will be packaged for final disposal at a geologic repository. The purpose of this study is to evaluate two alternatives for interim Phase 1 storage of K Basin sludge. The cost, schedule, and risks for sludge storage at a newly-constructed Alternate Storage Facility (ASF) are compared to those at T Plant, which has been used previously for sludge storage. Based on the results of the assessment, T Plant is recommended for Phase 1 interim storage of sludge. Key elements that support this recommendation are the following: (1) T Plant has a proven process for storing sludge; (2) T Plant storage can be implemented at a lower incremental cost than the ASF; and (3) T Plant storage has a more favorable schedule profile, which provides more float, than the ASF. Underpinning the recommendation of T Plant for sludge storage is the assumption that T Plant has a durable, extended mission independent of the K Basin sludge interim storage mission. If this assumption cannot be validated and the operating costs of T Plant are borne by the Sludge Treatment Project, the conclusions and recommendations of this study would change. The following decision-making strategy, which is

  14. Central and Eastern United States (CEUS) Seismic Source Characterization (SSC) for Nuclear Facilities Project

    SciTech Connect

    Kevin J. Coppersmith; Lawrence A. Salomone; Chris W. Fuller; Laura L. Glaser; Kathryn L. Hanson; Ross D. Hartleb; William R. Lettis; Scott C. Lindvall; Stephen M. McDuffie; Robin K. McGuire; Gerry L. Stirewalt; Gabriel R. Toro; Robert R. Youngs; David L. Slayter; Serkan B. Bozkurt; Randolph J. Cumbest; Valentina Montaldo Falero; Roseanne C. Perman' Allison M. Shumway; Frank H. Syms; Martitia P. Tuttle

    2012-01-31

    Seismic Hazard Analysis: Guidance on Uncertainty and Use of Experts. The model will be used to assess the present-day composite distribution for seismic sources along with their characterization in the CEUS and uncertainty. In addition, this model is in a form suitable for use in PSHA evaluations for regulatory activities, such as Early Site Permit (ESPs) and Combined Operating License Applications (COLAs). Applications, Values, and Use Development of a regional CEUS seismic source model will provide value to those who (1) have submitted an ESP or COLA for Nuclear Regulatory Commission (NRC) review before 2011; (2) will submit an ESP or COLA for NRC review after 2011; (3) must respond to safety issues resulting from NRC Generic Issue 199 (GI-199) for existing plants and (4) will prepare PSHAs to meet design and periodic review requirements for current and future nuclear facilities. This work replaces a previous study performed approximately 25 years ago. Since that study was completed, substantial work has been done to improve the understanding of seismic sources and their characterization in the CEUS. Thus, a new regional SSC model provides a consistent, stable basis for computing PSHA for a future time span. Use of a new SSC model reduces the risk of delays in new plant licensing due to more conservative interpretations in the existing and future literature. Perspective The purpose of this study, jointly sponsored by EPRI, the U.S. Department of Energy (DOE), and the NRC was to develop a new CEUS SSC model. The team assembled to accomplish this purpose was composed of distinguished subject matter experts from industry, government, and academia. The resulting model is unique, and because this project has solicited input from the present-day larger technical community, it is not likely that there will be a need for significant revision for a number of years. See also Sponsors Perspective for more details. The goal of this project was to implement the CEUS SSC work plan

  15. Status Review of Wildlife Mitigation, Columbia Basin Hydroelectric Projects, Washington Facilities (Intrastate) Final Report.

    SciTech Connect

    Howerton, Jack

    1984-11-01

    This report was prepared for BPA in fulfillment of section 1004 (b)(1) of the Pacific Northwest Electric Power Planning and Conservation Act of 1980, to review the status of past, present, and proposed future wildlife planning and mitigation program at existing hydroelectric projects in the Columbia River Basin. The project evaluations will form the basis for determining any needed remedial measures or additional project analysis. Projects addressed are: Merwin Dam; Swift Project; Yale Project; Cowlitz River; Boundary Dam; Box Canyon Dam; Lake Chelan; Condit Project; Enloe Project; Spokane River; Tumwater and Dryden Dam; Yakima; and Naches Project.

  16. Cold test plan for the Old Hydrofracture Facility tank contents removal project, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1997-11-01

    This Old Hydrofracture Facility (OHF) Tanks Contents Removal Project Cold Test Plan describes the activities to be conducted during the cold test of the OHF sluicing and pumping system at the Tank Technology Cold Test Facility (TTCTF). The TTCTF is located at the Robotics and Process Systems Complex at the Oak Ridge National Laboratory (ORNL). The cold test will demonstrate performance of the pumping and sluicing system, fine-tune operating instructions, and train the personnel in the actual work to be performed. After completion of the cold test a Technical Memorandum will be prepared documenting completion of the cold test, and the equipment will be relocated to the OHF site.

  17. Systems and methods for deactivating a matrix converter

    SciTech Connect

    Ransom, Ray M.

    2013-04-02

    Systems and methods are provided for deactivating a matrix conversion module. An electrical system comprises an alternating current (AC) interface, a matrix conversion module coupled to the AC interface, an inductive element coupled between the AC interface and the matrix conversion module, and a control module. The control module is coupled to the matrix conversion module, and in response to a shutdown condition, the control module is configured to operate the matrix conversion module to deactivate the first conversion module when a magnitude of a current through the inductive element is less than a threshold value.

  18. Closure of the Fast Flux Test Facility: current status and future plans

    SciTech Connect

    Lesperance, C. P.; Doebler, S. V.; Burke, T. M.

    2007-07-01

    The Fast Flux Test Facility (FFTF) was a 400 MWt sodium-cooled fast reactor situated on the U.S. Department of Energy's (DOE) Hanford Site in the southeastern portion of Washington State. DOE issued the final order to shut down the facility in 2001, when it was concluded that there was no longer a need for FFTF. Deactivation activities are in progress to remove or stabilize major hazards and deactivate systems to achieve end points documented in the project baseline. The reactor has been de-fueled, and approximately 97% of the fuel has been removed from the facility. Approximately 97% of the sodium has been drained from the plant's systems and placed into an on-site Sodium Storage Facility. The residual sodium will be kept frozen under a blanket of inert gas until it is removed later as part of the facility's decontamination and decommissioning (D and D). Plant systems have been shut down and placed in a low-risk state to minimize requirements for surveillance and maintenance. D and D work cannot begin until an Environmental Impact Statement has been prepared to evaluate various end state options and to provide a basis for selecting one of the options. The Environmental Impact Statement is expected to be issued in 2009. (authors)

  19. CLOSURE OF THE FAST FLUX TEST FACILITY (FFTF) CURRENT STATUS & FUTURE PLANS

    SciTech Connect

    LESPERANCE, C.P.

    2007-05-23

    The Fast Flux Test Facility (FFTF) was a 400 MWt sodium-cooled fast reactor situated on the U.S. Department of Energy's (DOE) Hanford Site in the southeastern portion of Washington State. DOE issued the final order to shut down the facility in 2001, when it was concluded that there was no longer a need for FFTF. Deactivation activities are in progress to remove or stabilize major hazards and deactivate systems to achieve end points documented in the project baseline. The reactor has been defueled, and approximately 97% of the fuel has been removed from the facility. Approximately 97% of the sodium has been drained from the plant's systems and placed into an on-site Sodium Storage Facility. The residual sodium will be kept frozen under a blanket of inert gas until it is removed later as part of the facility's decontamination and decommissioning (D&D). Plant systems have been shut down and placed in a low-risk state to minimize requirements for surveillance and maintenance. D&D work cannot begin until an Environmental Impact Statement has been prepared to evaluate various end state options and to provide a basis for selecting one of the options. The Environmental Impact Statement is expected to be issued in 2009.

  20. Design criteria document, Maintenance Shop/Support Facility, K-Basin Essential Systems Recovery, Project W-405

    SciTech Connect

    Strehlow, M.W.B.

    1994-12-14

    During the next 10 years a substantial amount of work is scheduled in the K-Basin Area related to the storage and eventual removal of irradiated N-Reactor fuel. Currently, maintenance support activities are housed in existing structures that were constructed in the early 1950`s. These forty-year-old facilities and their supporting services are substandard, leading to inefficiencies. Because of numerous identified deficiencies and the planned increase in the numbers of K-Basin maintenance personnel, adequate maintenance support facilities that allow efficient operations are needed. The objective of this sub-project of Project W-405 is to provide a maintenance and storage facility which meets the K-Basin Maintenance Organization requirements as defined in Attachment 1. In Reference A, existing guidelines and requirements were used to allocate space for the maintenance activities and to provide a layout concept (See Attachment 2). The design solution includes modifying the existing 190 K-E building to provide space for shops, storage, and administration support functions. The primary reason for the modification is to simplify siting/permitting and make use of existing infrastructure. In addition, benefits relative to design loads will be realized by having the structure inside 190K-E. The new facility will meet the Maintenance Organization approved requirements in Attachment 1 relating to maintenance activities, storage areas, and personnel support services. This sub-project will also resolve outstanding findings and/or deficiencies relating to building fire protection, HVAC requirements, lighting replacement/upgrades, and personnel facilities. Compliance with building codes, local labor agreements and safety standards will result.

  1. CASE STUDY PROJECT: THE USE OF LOW-VOC/HAP COATINGS AT WOOD FURNITURE MANUFACTURING FACILITIES

    EPA Science Inventory

    The paper discusses a study of pollution prevention and the use of low-VOC/HAP (volatile organic compound/hazardous air pollutant) coatings at wood furniture manufacturing facilities. The study is to identify wood furniture and cabinet manufacturing facilities that have converted...

  2. Documentation assessment, Project C-018H, 200-E area effluent treatment facility

    SciTech Connect

    Peres, M.W.; Connor, M.D.; Mertelendy, J.I.

    1994-12-21

    Project C-018H is one of the fourteen subprojects to the Hanford Environmental Compliance (HEC) Project. Project C-018H provides treatment and disposal for the 242-A Evaporator and PUREX plant process condensate waste streams. This project used the Integrated Management Team (IMT) approach proposed by RL. The IMT approach included all affected organizations on the project team to coordinate and execute all required project tasks, while striving to integrate and satisfy all technical, operational, functional, and organizational objectives. The HEC Projects were initiated in 1989. Project C-018H began in early 1990, with completion of construction currently targeted for mid-1995. This assessment was performed to evaluate the effectiveness of the management control on design documents and quality assurance records developed and submitted for processing, use, and retention for the Project. The assessment focused primarily on the overall adequacy and quality of the design documentation currently being submitted to the project document control function.

  3. Design and construction of the defense waste processing facility project at the Savannah River Plant

    SciTech Connect

    Baxter, R G

    1986-01-01

    The Du Pont Company is building for the Department of Energy a facility to vitrify high-level radioactive waste at the Savannah River Plant (SRP) near Aiken, South Carolina. The Defense Waste Processing Facility (DWPF) will solidify existing and future radioactive wastes by immobilizing the waste in Processing Facility (DWPF) will solidify existing and future radioactives wastes by immobilizing the waste in borosilicate glass contained in stainless steel canisters. The canisters will be sealed, decontaminated and stored, prior to emplacement in a federal repository. At the present time, engineering and design is 90% complete, construction is 25% complete, and radioactive processing in the $870 million facility is expected to begin by late 1989. This paper describes the SRP waste characteristics, the DWPF processing, building and equipment features, and construction progress of the facility.

  4. Final report of the decontamination and decommissioning of Building 34 at the Grand Junction Projects Office Facility

    SciTech Connect

    Widdop, M.R.

    1996-08-01

    The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7 acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the Grand Junction Projects Office Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, was also the remedial action contractor. Building 34 was radiologically contaminated and the building was demolished in 1996. The soil area within the footprint of the building was analyzed and found to be not contaminated. The area can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual closeout report for each contaminated GJPO building.

  5. Mixed and Low-Level Waste Treatment Facility project. Appendix A, Environmental and regulatory planning and documentation: Draft

    SciTech Connect

    Not Available

    1992-04-01

    Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report, Appendix A, Environmental & Regulatory Planning & Documentation, identifies the regulatory requirements that would be imposed on the operation or construction of a facility designed to process the INEL`s waste streams. These requirements are contained in five reports that discuss the following topics: (1) an environmental compliance plan and schedule, (2) National Environmental Policy Act requirements, (3) preliminary siting requirements, (4) regulatory justification for the project, and (5) health and safety criteria.

  6. 327 Building liquid waste handling options modification project plan

    SciTech Connect

    Ham, J.E.

    1998-03-28

    This report evaluates the modification options for handling radiological liquid waste (RLW) generated during decontamination and cleanout of the 327 Building. The overall objective of the 327 Facility Stabilization Project is to establish a passively safe and environmentally secure configuration of the 327 Facility. The issue of handling of RLW from the 327 Facility (assuming the 34O Facility is not available to accept the RLW) has been conceptually examined in at least two earlier engineering studies (Parsons 1997a and Hobart l997). Each study identified a similar preferred alternative that included modifying the 327 Facility RLWS handling systems to provide a truck load-out station, either within the confines of the facility or exterior to the facility. The alternatives also maximized the use of existing piping, tanks, instrumentation, controls and other features to minimize costs and physical changes. An issue discussed in each study involved the anticipated volume of the RLW stream. Estimates ranged between 113,550 and 387,500 liters in the earlier studies. During the development of the 324/327 Building Stabilization/Deactivation Project Management Plan, the lower estimate of approximately 113,550 liters was confirmed and has been adopted as the baseline for the 327 Facility RLW stream. The goal of this engineering study is to reevaluate the existing preferred alternative and select a new preferred alternative, if appropriate. Based on the new or confirmed preferred alternative, this study will also provide a conceptual design and cost estimate for required modifications to the 327 Facility to allow removal of RLWS and treatment of the RLW generated during deactivation.

  7. Features of deactivation of industrial catalysts in the Claus process

    SciTech Connect

    Kasumov, F.B.; Dzhafarova, E.M.; Dzhafarova, S.A.; Nadalieva, Yu.R.; Kerimov, I.Ya.

    1993-10-20

    The deactivation degree of samples of industrial alumina Claus catalyst after 3 yr usage has been determined. The samples have been selected from certain layers at four points of the catalyst volume under the continuous converter operation by the specially constructed device.

  8. Mediation Analysis of Mode Deactivation Therapy (Reanalysis and Interpretation)

    ERIC Educational Resources Information Center

    Bass, Christopher K.; Apsche, Jack A.

    2013-01-01

    A key component of Mode Deactivation Therapy (MDT) is the development of self-awareness and regulatory skills by the client with the aim of helping adolescent males with conduct disordered behaviors, including sexually inappropriate behaviors and emotional dysregulation. The goal includes altering specific behaviors to fall within socially…

  9. 42 CFR 424.540 - Deactivation of Medicare billing privileges.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 42 Public Health 3 2013-10-01 2013-10-01 false Deactivation of Medicare billing privileges. 424.540 Section 424.540 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) MEDICARE PROGRAM (CONTINUED) CONDITIONS FOR MEDICARE PAYMENT Requirements...

  10. 42 CFR 424.540 - Deactivation of Medicare billing privileges.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 42 Public Health 3 2010-10-01 2010-10-01 false Deactivation of Medicare billing privileges. 424.540 Section 424.540 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) MEDICARE PROGRAM CONDITIONS FOR MEDICARE PAYMENT Requirements...

  11. 42 CFR 424.540 - Deactivation of Medicare billing privileges.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 42 Public Health 3 2012-10-01 2012-10-01 false Deactivation of Medicare billing privileges. 424.540 Section 424.540 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) MEDICARE PROGRAM (CONTINUED) CONDITIONS FOR MEDICARE PAYMENT Requirements...

  12. 42 CFR 424.540 - Deactivation of Medicare billing privileges.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 42 Public Health 3 2011-10-01 2011-10-01 false Deactivation of Medicare billing privileges. 424.540 Section 424.540 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) MEDICARE PROGRAM CONDITIONS FOR MEDICARE PAYMENT Requirements...

  13. 42 CFR 424.540 - Deactivation of Medicare billing privileges.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 42 Public Health 3 2014-10-01 2014-10-01 false Deactivation of Medicare billing privileges. 424.540 Section 424.540 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) MEDICARE PROGRAM (CONTINUED) CONDITIONS FOR MEDICARE PAYMENT Requirements...

  14. A Summary of Published Mode Deactivation Therapy Articles

    ERIC Educational Resources Information Center

    Apsche, Jack A.

    2006-01-01

    This article summarizes all of the Mode Deactivation Therapy, (MDT) articles published to date. MDT has shown to be more effective than Cognitive Behavior Therapy, (CBT), Social Skills Training, (SST), and Dialectical Behavior Therapy, (DBT), Apsche, Bass, Jennings, Murphy, Hunter, and Siv, (2005); Apsche & Bass, (2005); Apsche, Bass & Murphy,…

  15. Mode Deactivation Therapy (MDT) Family Therapy: A Theoretical Case Analysis

    ERIC Educational Resources Information Center

    Apsche, J. A.; Ward Bailey, S. R.

    2004-01-01

    This case study presents a theoretical analysis of implementing mode deactivation therapy (MDT) (Apsche & Ward Bailey, 2003) family therapy with a 13 year old Caucasian male. MDT is a form of cognitive behavioral therapy (CBT) that combines the balance of dialectical behavior therapy (DBT) (Linehan, 1993), the importance of perception from…

  16. Compassionate deactivation of ventricular assist devices in pediatric patients.

    PubMed

    Hollander, Seth A; Axelrod, David M; Bernstein, Daniel; Cohen, Harvey J; Sourkes, Barbara; Reddy, Sushma; Magnus, David; Rosenthal, David N; Kaufman, Beth D

    2016-05-01

    Despite greatly improved survival in pediatric patients with end-stage heart failure through the use of ventricular assist devices (VADs), heart failure ultimately remains a life-threatening disease with a significant symptom burden. With increased demand for donor organs, liberalizing the boundaries of case complexity, and the introduction of destination therapy in children, more children can be expected to die while on mechanical support. Despite this trend, guidelines on the ethical and pragmatic issues of compassionate deactivation of VAD support in children are strikingly absent. As VAD support for pediatric patients increases in frequency, the pediatric heart failure and palliative care communities must work toward establishing guidelines to clarify the complex issues surrounding compassionate deactivation. Patient, family and clinician attitudes must be ascertained and education regarding the psychological, legal and ethical issues should be provided. Furthermore, pediatric-specific planning documents for use before VAD implantation as well as deactivation checklists should be developed to assist with decision-making at critical points during the illness trajectory. Herein we review the relevant literature regarding compassionate deactivation with a specific focus on issues related to children. PMID:27197773

  17. Hot Gas Cleanup Test Facility for Gasification and Pressurized Combustion Project. Quarterly report, April--June 1996

    SciTech Connect

    1996-12-31

    The objective of this project is to evaluate hot gas particle control technologies using coal-derived as streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed Include the integration of the particulate control devices into coal utilization systems, on-line cleaning, techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scale-up of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing, Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the original Transport Reactor gas source and Hot Gas Cleanup Units: 1 . Carbonizer/Pressurized Circulating, Fluidized Bed Gas Source; 2. Hot Gas Cleanup Units to mate to all gas streams; 3. Combustion Gas Turbine; 4. Fuel Cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF). The major emphasis during, this reporting period was continuing, the detailed design of the FW portion of the facility towards completion and integrating the balance-of-plant processes and particulate control devices (PCDS) into the structural and process designs. Substantial progress in construction activities was achieved during the quarter. Delivery and construction of the process structural steel is complete and the construction of steel for the coal preparation structure is complete.

  18. Transuranic waste projections at SRS for long range planning

    SciTech Connect

    Hootman, H.E.; Cook, J.R.

    1994-05-01

    This report predicts 30 year receipts of solid transuranic (TRU) wastes from eventual plutonium facility deactivation and cleanup, and combines them with the existing TRU waste holdings to provide a technical and quantitative basis for interim and long range TRU waste management planning. The current TRU waste holdings have been characterized based on data from the Computerized Radioactive Waste Burial Records Analysis (COBRA) system. Six TRU waste disposition categories have been identified for existing TRU waste as shown in Table 1. An additional category has been quantified that includes projected waste volumes from the Decontamination and Decommissioning (D&D) of TRU waste generating facilities. These projections are based on COBRA data from D&D of the original plutonium finishing facilities in F and H Areas that were replaced in the 1970`s and 80`s.

  19. Spent nuclear fuel project cold vacuum drying facility supporting data and calculation database

    SciTech Connect

    IRWIN, J.J.

    1999-02-26

    This document provides a database of supporting calculations for the Cold Vacuum Drying Facility (CVDF). The database was developed in conjunction with HNF-SD-SNF-SAR-002, ''Safety Analysis Report for the Cold Vacuum Drying Facility'', Phase 2, ''Supporting Installation of Processing Systems'' (Garvin 1998). The HNF-SD-SNF-DRD-002, 1997, ''Cold Vacuum Drying Facility Design Requirements'', Rev. 2, and the CVDF Summary Design Report. The database contains calculation report entries for all process, safety and facility systems in the CVDF, a general CVD operations sequence and the CVDF System Design Descriptions (SDDs). This database has been developed for the SNFP CVDF Engineering Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

  20. ALARA plan for the Old Hydrofracture Facility tanks contents removal project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1998-04-01

    The purpose of the Old Hydrofracture Facility (OHF) Tanks Contents Removal Project is to remove the liquid low-level waste from the five underground storage tanks located at OHF and transfer the resulting slurry to the Melton Valley Storage Tanks facility for treatment and disposal. Among the technical objectives for the OHF Project, there is a specific provision to maintain personnel exposures as low as reasonably achievable (ALARA) during each activity of the project and to protect human health and the environment. The estimated doses and anticipated conditions for accomplishing this project are such that an ALARA Plan is necessary to facilitate formal radiological review of the campaign. This ALARA Plan describes the operational steps necessary for accomplishing the job together with the associated radiological impacts and planned controls. Individual and collective dose estimates are also provided for the various tasks. Any significant changes to this plan (i.e., planned exposures that are greater than 10% of original dose estimates) will require formal revision and concurrence from all parties listed on the approval page. Deviations from this plan (i.e., work outside the scope covered by this plan) also require the preparation of a task-specific ALARA Review that will be amended to this plan with concurrence from all parties listed on the approval page.

  1. Final report of the decontamination and decommissioning of Building 18 at the Grand Junction Projects Office Facility

    SciTech Connect

    Widdop, M.R.

    1996-08-01

    The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, also is the remedial action contractor. The soil beneath Building 18 was found to be radiologically contaminated; the building was not contaminated. The soil was remediated in accordance with identified standards. Building 18 and the underlying soil can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.

  2. Creation of a neonatology facility in a developing country: experience from a 5-year project in China.

    PubMed

    Peabody, J W; Hesketh, T; Kattwinkel, J

    1992-01-01

    In 1983, Project HOPE was invited by Zhejiang Medical University to collaborate in developing a neonatal intensive care unit (NICU) at the Children's Hospital in Hangzhou, China. The initial approach involved renovating facilities, purchasing equipment and supplies, placing short-term consultants in the unit as teachers, and bringing selected leaders to the United States for brief fellowships. An evaluation at 18 months disclosed poor organization and leadership, inconsistent clinical care, and unsatisfactory utilization and maintenance of facilities and equipment. Therefore the strategy was revised to include long-term physician and nursing consultants, establishment of ties with HOPE Biomedical Engineering projects, and development of formal education programs. The unit was transferred to the Chinese after 4 years and an evaluation 1 year after transfer revealed an actively functioning independent NICU with evolving effective leadership, established purchasing and preventive maintenance programs, and continuing formal education activities. Unsatisfactory progress was found with the development of a transport system, some laboratory capabilities, adherence to admission and discharge policies, and various other administrative issues. Although the goal of establishing an independent NICU was realized, perhaps the most lasting accomplishment was the establishment of a facility and a format for development of a transportable education program aimed at improving neonatal care practices throughout a larger region of China. PMID:1418144

  3. Annual report for RCRA groundwater monitoring projects at Hanford Site facilities for 1995

    SciTech Connect

    Hartman, M.J.

    1996-02-01

    This report presents the annual hydrogeologic evaluation of 19 Resource Conservation and Recovery Act of 1976 facilities and 1 nonhazardous waste facility at the US Department of Energy`s Hanford Site. Although most of the facilities no longer receive dangerous waste, a few facilities continue to receive dangerous waste constituents for treatment, storage, or disposal. The 19 Resource Conservation and Recovery Act facilities comprise 29 waste management units. Nine of the units are monitored under groundwater quality assessment status because of elevated levels of contamination indicator parameters. The impact of those units on groundwater quality, if any, is being investigated. If dangerous waste or waste constituents have entered groundwater, their concentration profiles, rate, and extent of migration are evaluated. Groundwater is monitored at the other 20 units to detect leakage, should it occur. This report provides an interpretation of groundwater data collected at the waste management units between October 1994 and September 1995. Groundwater quality is described for the entire Hanford Site. Widespread contaminants include nitrate, chromium, carbon tetrachloride, tritium, and other radionuclides.

  4. Spent nuclear fuel project cold vacuum drying facility process water conditioning system design description

    SciTech Connect

    IRWIN, J.J.

    1998-11-30

    This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Process Water Conditioning (PWC) System. The SDD was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), the HNF-SD-SNF-DRD-O02, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the PWC equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

  5. Facility Effluent Monitoring Plan for the Spent Nuclear Fuel (SNF) Project

    SciTech Connect

    HUNACEK, G.S.

    2000-08-01

    A facility effluent monitoring plan is required by the US. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document was prepared using the specific guidelines identified in Westinghouse Hanford Company (WHC)-EP-0438-1, ''A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans'', and assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the third revision to the original annual report. This document is reviewed annually even if there are no operational changes, and it is updated as necessary.

  6. Spent nuclear fuel project cold vacuum drying facility vacuum and purge system design description

    SciTech Connect

    IRWIN, J.J.

    1998-11-30

    This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Vacuum and Purge System (VPS) . The SDD was developed in conjunction with HNF-SD-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-002, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the VPS equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

  7. SLUDGE TREATMENT PROJECT KOP DISPOSITION - THERMAL AND GAS ANALYSIS FOR THE COLD VACUUM DRYING FACILITY

    SciTech Connect

    SWENSON JA; CROWE RD; APTHORPE R; PLYS MG

    2010-03-09

    The purpose of this document is to present conceptual design phase thermal process calculations that support the process design and process safety basis for the cold vacuum drying of K Basin KOP material. This document is intended to demonstrate that the conceptual approach: (1) Represents a workable process design that is suitable for development in preliminary design; and (2) Will support formal safety documentation to be prepared during the definitive design phase to establish an acceptable safety basis. The Sludge Treatment Project (STP) is responsible for the disposition of Knock Out Pot (KOP) sludge within the 105-K West (KW) Basin. KOP sludge consists of size segregated material (primarily canister particulate) from the fuel and scrap cleaning process used in the Spent Nuclear Fuel process at K Basin. The KOP sludge will be pre-treated to remove fines and some of the constituents containing chemically bound water, after which it is referred to as KOP material. The KOP material will then be loaded into a Multi-Canister Overpack (MCO), dried at the Cold Vacuum Drying Facility (CVDF) and stored in the Canister Storage Building (CSB). This process is patterned after the successful drying of 2100 metric tons of spent fuel, and uses the same facilities and much of the same equipment that was used for drying fuel and scrap. Table ES-l present similarities and differences between KOP material and fuel and between MCOs loaded with these materials. The potential content of bound water bearing constituents limits the mass ofKOP material in an MCO load to a fraction of that in an MCO containing fuel and scrap; however, the small particle size of the KOP material causes the surface area to be significantly higher. This relatively large reactive surface area represents an input to the KOP thermal calculations that is significantly different from the calculations for fuel MCOs. The conceptual design provides for a copper insert block that limits the volume available to

  8. Waste Tank Size Determination for the Hanford River Protection Project Cold Test, Training, and Mockup Facility

    SciTech Connect

    Onishi, Yasuo; Wells, Beric E.; Kuhn, William L.

    2001-03-30

    The objective of the study was to determine the minimum tank size for the Cold Test Facility process testing of Hanford tank waste. This facility would support retrieval of waste in 75-ft-diameter DSTs with mixer pumps and SSTs with fluidic mixers. The cold test model will use full-scale mixer pumps, transfer pumps, and equipment with simulated waste. The study evaluated the acceptability of data for a range of tank diameters and depths and included identifying how the test data would be extrapolated to predict results for a full-size tank.

  9. Los Alamos plutonium facility applied systems integration project status report for period ending August 31, 1981

    SciTech Connect

    Shirk, D.G.; Bearse, R.C.; Marshall, R.S.; Baker, A.L.; Thomas, C.C. Jr.

    1982-02-01

    The conceptual design of an on-line, near-real-time nondestructive assay instrumentation network for the Los Alamos Plutonium Facility is complete. Analysis of instrument history data indicates that the instrument certification procedures need improvement. Analysis of exhaust filter data has led to the derivation of a buildup prediction equation that is a function of throughput. This suggests that development of a generalized model is possible. A number of routine reports are now available from the Plutonium Facility/Los Alamos Safeguards System including inventories and active reports.

  10. Technical documentation in support of the project-specific analysis for construction and operation of the National Ignition Facility

    SciTech Connect

    Lazaro, M.A.; Vinikour, W.; Allison, T.

    1996-09-01

    This document provides information that supports or supplements the data and impact analyses presented in the National Ignition Facility (NIF) Project-Specific Analysis (PSA). The purposes of NIF are to achieve fusion ignition in the laboratory for the first time with inertial confinement fusion (ICF) technology and to conduct high- energy-density experiments ins support of national security and civilian application. NIF is an important element in the DOE`s science-based SSM Program, a key mission of which is to ensure the reliability of the nation`s enduring stockpile of nuclear weapons. NIF would also advance the knowledge of basic and applied high-energy- density science and bring the nation a large step closer to developing fusion energy for civilian use. The NIF PSA includes evaluations of the potential environmental impacts of constructing and operating the facility at one of five candidate site and for two design options.

  11. 105-K Basin material design basis feed description for spent nuclear fuel project facilities. Volume 2: Sludge

    SciTech Connect

    Pearce, K.L.

    1998-08-30

    Volume 2 provides the design feed compositions for the baseline K East and K West Basin sludge process streams expected to be generated during Spent Nuclear Fuel (SNF) Project activities. Four types of feeds are required to support evaluation of specific facility and process considerations during the development of new facilities and processes. These four design feeds provide nominal and bounding conditions for design evaluations. Volume 2 includes definition of inventories for: (1) KE and KW Basins sludge locations (pit sludges, floor sludge, canister.sludge, and wash sludge components), (2) nominal feed for each of five process feed streams, (3) shielding design feed, (4) safety/regulatory assessment feed, and (5) criticality assessment feed.

  12. A Microsoft Project-Based Planning, Tracking, and Management Tool for the National Transonic Facility's Model Changeover Process

    NASA Technical Reports Server (NTRS)

    Vairo, Daniel M.

    1998-01-01

    The removal and installation of sting-mounted wind tunnel models in the National Transonic Facility (NTF) is a multi-task process having a large impact on the annual throughput of the facility. Approximately ten model removal and installation cycles occur annually at the NTF with each cycle requiring slightly over five days to complete. The various tasks of the model changeover process were modeled in Microsoft Project as a template to provide a planning, tracking, and management tool. The template can also be used as a tool to evaluate improvements to this process. This document describes the development of the template and provides step-by-step instructions on its use and as a planning and tracking tool. A secondary role of this document is to provide an overview of the model changeover process and briefly describe the tasks associated with it.

  13. Environmental assessment of facility operations at the U.S. Department of Energy Grand Junction Projects Office, Grand Junction, Colorado

    SciTech Connect

    1996-06-01

    The US Department of Energy (DOE) has prepared a sitewide environmental assessment (EA) of the proposed action to continue and expand present-day activities on the DOE Grand Junction Projects Office (GJPO) facility in Grand Junction, Colorado. Because DOE-GJPO regularly proposes and conducts many different on-site activities, DOE decided to evaluate these activities in one sitewide EA rather than in multiple, activity-specific documents. On the basis of the information and analyses presented in the EA, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment, as defined by the National Environmental Policy Act (NEPA) of 1969. Therefore, preparation of an environmental impact statement is not required for facility operations, and DOE is issuing this Finding of No Significant Impact (FONSI).

  14. Recent developments in the Los Alamos National Laboratory Plutonium Facility Waste Tracking System-automated data collection pilot project

    SciTech Connect

    Martinez, B.; Montoya, A.; Klein, W.

    1999-02-01

    The waste management and environmental compliance group (NMT-7) at the Los Alamos National Laboratory has initiated a pilot project for demonstrating the feasibility and utility of automated data collection as a solution for tracking waste containers at the Los Alamos National Laboratory Plutonium Facility. This project, the Los Alamos Waste Tracking System (LAWTS), tracks waste containers during their lifecycle at the facility. LAWTS is a two-tiered system consisting of a server/workstation database and reporting engine and a hand-held data terminal-based client program for collecting data directly from tracked containers. New containers may be added to the system from either the client unit or from the server database. Once containers are in the system, they can be tracked through one of three primary transactions: Move, Inventory, and Shipment. Because LAWTS is a pilot project, it also serves as a learning experience for all parties involved. This paper will discuss many of the lessons learned in implementing a data collection system in the restricted environment. Specifically, the authors will discuss issues related to working with the PPT 4640 terminal system as the data collection unit. They will discuss problems with form factor (size, usability, etc.) as well as technical problems with wireless radio frequency functions. They will also discuss complications that arose from outdoor use of the terminal (barcode scanning failures, screen readability problems). The paper will conclude with a series of recommendations for proceeding with LAWTS based on experience to date.

  15. CENTRAL STORAGE FACILITY PROJECT IN COLOMBIA TO PROVIDE THE SAFE STORAGE AND PROTECTION OF HIGH-ACTIVITY RADIOACTIVE SOURCES

    SciTech Connect

    Greenberg, Raymond; Wright, Kyle A.; McCaw, Erica E.; Vallejo, Jorge

    2009-10-07

    The Global Threat Reduction Initiative (GTRI) reduces and protects vulnerable nuclear and radiological material located at civilian sites worldwide. Internationally, over 40 countries are cooperating with GTRI to enhance the security of these materials. The GTRI program has worked successfully with foreign countries to remove and protect nuclear and radioactive materials, including orphaned and disused high-activity sources. GTRI began cooperation with the Republic of Colombia in April 2004. This cooperation has been a resounding success by securing forty high-risk sites, consolidating disused/orphan sources at an interim secure national storage facility, and developing a comprehensive approach to security, training, and sustainability. In 2005 the Colombian Ministry of Mines and Energy requested the Department of Energy’s support in the construction of a new Central Storage Facility (CSF). In December 2005, the Ministry selected to construct this facility at the Institute of Geology and Mining (Ingeominas) site in Bogota. This site already served as Colombia’s national repository, where disused sources were housed in various buildings around the complex. The CSF project was placed under contract in May 2006, but environmental issues and public protests, which led to a class action lawsuit against the Colombian Government, forced the Ministry to quickly suspend activities, thereby placing the project in jeopardy. Despite these challenges, however, the Ministry of Mines and Energy worked closely with public and environmental authorities to resolve these issues, and continued to be a strong advocate of the GTRI program. In June 2008, the Ministry of Mines and Energy was granted the construction and environmental licenses. As a result, construction immediately resumed and the CSF was completed by December 2008. A commissioning ceremony was held for the new facility in January 2009, which was attended by representatives from the Department of Energy, U.S. Embassy

  16. Short-Term Effects of State Deregulation on the Adequacy and Equity of School Facility Projects.

    ERIC Educational Resources Information Center

    Kowalski, Theodore J.; Decman, John C.

    2002-01-01

    In 1995, the Indiana Legislature deregulated state controls over public-school construction projects by reducing the status of required specifications to guidelines. Also, local taxpayers were given greater authority to prevent proposed projects. This study examines the short-term effects of this policy shift. (Contains 5 tables and 16…

  17. Developing Renewable Energy Projects Larger Than 10 MWs at Federal Facilities (Book)

    SciTech Connect

    Not Available

    2013-03-01

    To accomplish Federal goals for renewable energy, sustainability, and energy security, large-scale renewable energy projects must be developed and constructed on Federal sites at a significant scale with significant private investment. The U.S. Department of Energy's Federal Energy Management Program (FEMP) helps Federal agencies meet these goals and assists agency personnel navigate the complexities of developing such projects and attract the necessary private capital to complete them. This guide is intended to provide a general resource that will begin to develop the Federal employee's awareness and understanding of the project developer's operating environment and the private sector's awareness and understanding of the Federal environment. Because the vast majority of the investment that is required to meet the goals for large-scale renewable energy projects will come from the private sector, this guide has been organized to match Federal processes with typical phases of commercial project development. The main purpose of this guide is to provide a project development framework to allow the Federal Government, private developers, and investors to work in a coordinated fashion on large-scale renewable energy projects. The framework includes key elements that describe a successful, financially attractive large-scale renewable energy project.

  18. Communications on School Facility Projects--A Promise to the Community.

    ERIC Educational Resources Information Center

    Craig, Joyce A.; DeJong, William S.; McComb, Scott

    1997-01-01

    Discusses Beaufort County School District's (South Carolina) "Facilities 2000" plan to simultaneously build and renovate multiple schools within one district and an oversight committee's communication efforts with the surrounding community. The committee's approach in providing accountability, monitoring progress, and reporting to the public are…

  19. Odor and chemical emissions from dairy and swine facilities: Part 1 - project overview and collection methods

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Livestock facilities have received numerous criticisms due to their emissions of odorous air and chemicals. Hence, there is a significant need for odor emission factors and identification of principle odorous chemicals. Odor emission factors are used as inputs to odor setback models, while chemica...

  20. Designs for Success: Massive Building Project Makes LACCD a Leader in Green Facilities

    ERIC Educational Resources Information Center

    LaVista, Daniel

    2010-01-01

    After a 35-year building hiatus, the nine colleges in the Los Angeles Community College District (LACCD) needed a major facelift. Facilities on LACCD campuses were antiquated and had fallen into disrepair. For years, students voiced dismay, saying their campuses resembled high schools rather than colleges. Inadequate infrastructure drove many…

  1. Status Review of Wildlife Mitigation at Columbia Basin Hydroelectric Projects, Oregon Facilities, Final Report.

    SciTech Connect

    Bedrossian, Karen L.

    1984-08-01

    The report presents a review and documentation of existing information on wildlife resources at Columbia River Basin hydroelectric facilities within Oregon. Effects of hydroelectric development and operation; existing agreements; and past, current and proposed wildlife mitigation, enhancement, and protection activities were considered. (ACR)

  2. The interaction of a metal deactivator with metal surfaces

    SciTech Connect

    Schreifels, J.A. ); Morris, R.E.; Turner, N.H.; Mowery, R.L. )

    1990-01-01

    In modern aircraft fuel systems, the fuel is used as a heat transfer medium to dissipate heat from the avionics and hydraulic systems. Under these conditions, the fuel can undergo autooxidations. Autooxidations of net fuel can result in the formation of insoluble gum and sediment which can impair operation of the jet engine. Metal deactivator additives (MDA) were developed to counteract the catalytic activity of dissolved metals. The authors have directed their efforts at ascertaining the various mechanisms by which MDA can act, particularly in accelerated stability testing. One objective of this study was to determine to what extent interactions with metal surfaces of the test apparent govern the effectiveness of metal deactivators. This paper describes an examination of metal surfaces exposed to MDA solutions to determine under what, if any, conditions metal passivation can occur.

  3. Series mechanism of enzyme deactivation. Characterization of intermediate forms.

    PubMed

    Gianfreda, L; Marrucci, G; Grizzuti, N; Greco, G

    1985-06-01

    Acid phosphatase (E.C. 3.1.3.2) undergoes complex thermal deactivation phenomena, as revealed by the two-slope pattern of the enzyme logarithmic-specific-activity versus time curves. The native enzyme first decays toward an equilibrium distribution of less, but still active, intermediate structures and these, in turn, undergo a final degradation to a completely inactive form. The effect of the experimental conditions at which the enzyme is kept during the deactivation process on the characteristics of these intermediate enzymatic structures has been investigated. The kinetic parameters of p-nitro-phenyl phosphate hydrolysis, as catalyzed by some of these intermediate forms, have been determined and the results compared to those obtained with the native enzyme. PMID:18553749

  4. Defining the structural relationship between kainate receptor deactivation and desensitization

    PubMed Central

    Dawe, G. Brent; Musgaard, Maria; Andrews, Elizabeth D.; Daniels, Bryan A.; Aurousseau, Mark R.P.; Biggin, Philip C.; Bowie, Derek

    2016-01-01

    Desensitization is an important mechanism that curtails the activity of ligand-gated ion-channels (LGICs). Although the structural basis of desensitization is not fully resolved, it is thought to be governed by the physicochemical properties of the bound ligand. Here, we show the importance of an allosteric cation binding pocket in controlling transitions between activated and desensitized states of rat kainate-type (KAR) ionotropic glutamate receptors (iGluRs). Tethering a positive charge to this pocket sustains KAR activation, preventing desensitization, whereas mutations that disrupt cation binding eliminate channel gating. These different outcomes explain the structural distinction between deactivation and desensitization. Deactivation occurs when the ligand unbinds before the cation, whereas desensitization proceeds if a ligand is bound without cation pocket occupancy. This sequence of events is absent from AMPA-type iGluRs, identifying cations as gatekeepers of KAR gating, a role unique among even closely-related LGICs. PMID:23955023

  5. On the puzzling deactivation mechanism of thymine after light irradiation

    SciTech Connect

    Gonzalez, Leticia; Gonzalez-Vazquez, Jesus; Samoylova, Elena; Schultz, Thomas

    2008-12-08

    The possible deactivation mechanisms of thymine after UV light irradiation are reviewed in the light of theoretical calculations. Recent experiments reveal that three transient species with lifetimes in the fs, ps, and ns regime are present in thymine. The possibility of ground or excited state tautomerization is explored and discarded. The role of {pi}{sigma}* states, as well as of the proposed minimum of the {pi}{pi}* excited state surface are assessed. In view of the obtained calculations and results available from the literature, the measured time scales can be tentatively attributed to a model involving different conical intersections between the {pi}{pi}*, n{pi}*, and the electronic ground state, as well as deactivation via the triplet states. Time-resolved photoelectron experiments supported by theoretical calculations are proposed to appraise the validity of this model.

  6. Novel C-Ring-Hydroxy-Substituted Controlled Deactivation Cannabinergic Analogues.

    PubMed

    Kulkarni, Shashank; Nikas, Spyros P; Sharma, Rishi; Jiang, Shan; Paronis, Carol A; Leonard, Michael Z; Zhang, Bin; Honrao, Chandrashekhar; Mallipeddi, Srikrishnan; Raghav, Jimit Girish; Benchama, Othman; Järbe, Torbjörn U C; Bergman, Jack; Makriyannis, Alexandros

    2016-07-28

    In pursuit of safer controlled-deactivation cannabinoids with high potency and short duration of action, we report the design, synthesis, and pharmacological evaluation of novel C9- and C11-hydroxy-substituted hexahydrocannabinol (HHC) and tetrahydrocannabinol (THC) analogues in which a seven atom long side chain, with or without 1'-substituents, carries a metabolically labile 2',3'-ester group. Importantly, in vivo studies validated our controlled deactivation approach in rodents and non-human primates. The lead molecule identified here, namely, butyl-2-[(6aR,9R,10aR)-1-hydroxy-9-(hydroxymethyl)-6,6-dimethyl-6a,7,8,9,10,10a-hexahydro-6H-benzo[c]chromen-3-yl]-2-methylpropanoate (AM7499), was found to exhibit remarkably high in vitro and in vivo potency with shorter duration of action than the currently existing classical cannabinoid agonists. PMID:27367336

  7. Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron-Activated Shield Wall

    SciTech Connect

    Michael R. Kruzic

    2008-06-01

    Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility (Figure 1) was used in the early to mid-1960s for testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles. The TCA facility, known as Corrective Action Unit 115, was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the Federal Facility Agreement and Consent Order. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously, provided technical decisions are made by an experienced decision maker within the site conceptual site model. Facility closure involved a seven-step decommissioning strategy. First, preliminary investigation activities were performed, including review of process knowledge documentation, targeted facility radiological and hazardous material surveys, concrete core drilling and analysis, shield wall radiological characterization, and discrete sampling, which proved to be very useful and cost-effective in subsequent decommissioning planning and execution and worker safety. Second, site setup and mobilization of equipment and personnel were completed. Third, early removal of hazardous materials, including asbestos, lead, cadmium, and oil, was performed ensuring worker safety during more invasive demolition activities. Process piping was to be verified void of contents. Electrical systems were de-energized and other systems were rendered free of residual energy. Fourth, areas of high radiological contamination were decontaminated using multiple methods. Contamination levels varied across the facility. Fixed beta/gamma contamination levels ranged up to 2 million disintegrations per minute (dpm)/100

  8. Vulnerability Assessments and Resilience Planning at Federal Facilities. Preliminary Synthesis of Project

    SciTech Connect

    Moss, R. H.; Delgado, A.; Malone, E L.

    2015-08-15

    U.S. government agencies are now directed to assess the vulnerability of their operations and facilities to climate change and to develop adaptation plans to increase their resilience. Specific guidance on methods is still evolving based on the many different available frameworks. Agencies have been experimenting with these frameworks and approaches. This technical paper synthesizes lessons and insights from a series of research case studies conducted by the investigators at facilities of the U.S. Department of Energy and the Department of Defense. The purpose of the paper is to solicit comments and feedback from interested program managers and analysts before final conclusions are published. The paper describes the characteristics of a systematic process for prioritizing needs for adaptation planning at individual facilities and examines requirements and methods needed. It then suggests a framework of steps for vulnerability assessments at Federal facilities and elaborates on three sets of methods required for assessments, regardless of the detailed framework used. In a concluding section, the paper suggests a roadmap to further develop methods to support agencies in preparing for climate change. The case studies point to several preliminary conclusions; (1) Vulnerability assessments are needed to translate potential changes in climate exposure to estimates of impacts and evaluation of their significance for operations and mission attainment, in other words into information that is related to and useful in ongoing planning, management, and decision-making processes; (2) To increase the relevance and utility of vulnerability assessments to site personnel, the assessment process needs to emphasize the characteristics of the site infrastructure, not just climate change; (3) A multi-tiered framework that includes screening, vulnerability assessments at the most vulnerable installations, and adaptation design will efficiently target high-risk sites and infrastructure

  9. Contingency plan for the Old Hydrofracture Facility tanks sluicing project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1996-10-01

    Lockheed Martin Energy Systems, Inc. (Energy Systems), plans to begin a sluicing (flushing) and pumping project to remove the contents from five inactive, underground storage tanks at the Old Hydrofracture Facility (OHF) at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The tank contents will be transferred to the Melton Valley Storage Tanks, which are part of the active waste treatment system at ORNL. The purpose of the project is to minimize the risk of leaking the highly radioactive material to the environment. The five OHF tanks each contain a layer of sludge and a layer of supernatant. Based on a sampling project undertaken in 1995, the sludge in the tanks has been characterized as transuranic and mixed waste and the supernatants have been characterized as mixed waste. The combined radioactivity of the contents of the five tanks is approximately 29,500 Ci. This contingency plan is based on the preliminary design for the project and describes a series of potential accident/release scenarios for the project. It outlines Energy Systems` preliminary plans for prevention, detection, and mitigation. Prevention/detection methods range from using doubly contained pipelines to alarmed sensors and automatic pump cutoff systems. Plans for mitigation range from pumping leaked fluids from the built-in tank drainage systems and cleaning up spilled liquids to personnel evacuation.

  10. Review of project definition studies of possible on-site uses of superconducting super collider assets and facilities. Final report

    SciTech Connect

    1994-12-01

    This document reports on the results of a peer review and evaluation of studies made of potential uses of assets from the terminated Superconducting Super Collider (SSC) project. These project definition studies focused on nine areas of use of major assets and facilities at the SSC site near Waxahachie, Texas. The studies were undertaken as part of the effort to maximize the value of the investment made in the SSC and were supported by two sets of grants, one to the Texas National Research Laboratory Commission (TNRLC) and the second to various universities and other institutions for studies of ideas raised by a public call for expressions of interest. The Settlement Agreement, recently signed by the Department of Energy (DOE) and TNRLC, provides for a division of SSC property. As part of the goal of maximizing the value of the SSC investment, the findings contained in this report are thus addressed to officials in both the Department and TNRLC. In addition, this review had several other goals: to provide constructive feedback to those doing the studies; to judge the benefits and feasibility (including funding prospects) of the projects studied; and to help worthy projects become reality by matching projects with possible funding sources.

  11. Review of project definition studies of possible on-site uses of superconducting super collider assets and facilities

    SciTech Connect

    1994-12-01

    This document reports on the results of a peer review and evaluation of studies made of potential uses of assets from the terminated Superconducting Super Collider (SSC) project. These project definition studies focused on nine areas of use of major assets and facilities at the SSC site near Waxahachie, Texas. The studies were undertaken as part of the effort to maximize the value of the investment made in the SSC and were supported by two sets of grants, one to the Texas National Research Laboratory Commission (TNRLC) and the second to various universities and other institutions for studies of ideas raised by a public call for expressions of interest. The Settlement Agreement, recently signed by the Department of Energy (DOE) and TNRLC, provides for a division of SSC property. As part of the goal of maximizing the value of the SSC investment, the findings contained in this report are thus addressed to officials in both the Department and TNRLC. In addition, this review had several other goals: to provide constructive feedback to those doing the studies; to judge the benefits and feasibility (including funding prospects) of the projects studied; and to help worthy projects become reality by matching projects with possible funding sources.

  12. Mechanism of acetaldehyde-induced deactivation of microbial lipases

    PubMed Central

    2011-01-01

    Background Microbial lipases represent the most important class of biocatalysts used for a wealth of applications in organic synthesis. An often applied reaction is the lipase-catalyzed transesterification of vinyl esters and alcohols resulting in the formation of acetaldehyde which is known to deactivate microbial lipases, presumably by structural changes caused by initial Schiff-base formation at solvent accessible lysine residues. Previous studies showed that several lipases were sensitive toward acetaldehyde deactivation whereas others were insensitive; however, a general explanation of the acetaldehyde-induced inactivation mechanism is missing. Results Based on five microbial lipases from Candida rugosa, Rhizopus oryzae, Pseudomonas fluorescens and Bacillus subtilis we demonstrate that the protonation state of lysine ε-amino groups is decisive for their sensitivity toward acetaldehyde. Analysis of the diverse modification products of Bacillus subtilis lipases in the presence of acetaldehyde revealed several stable products such as α,β-unsaturated polyenals, which result from base and/or amino acid catalyzed aldol condensation of acetaldehyde. Our studies indicate that these products induce the formation of stable Michael-adducts at solvent-accessible amino acids and thus lead to enzyme deactivation. Further, our results indicate Schiff-base formation with acetaldehyde to be involved in crosslinking of lipase molecules. Conclusions Differences in stability observed with various commercially available microbial lipases most probably result from different purification procedures carried out by the respective manufacturers. We observed that the pH of the buffer used prior to lyophilization of the enzyme sample is of utmost importance. The mechanism of acetaldehyde-induced deactivation of microbial lipases involves the generation of α,β-unsaturated polyenals from acetaldehyde which subsequently form stable Michael-adducts with the enzymes. Lyophilization of

  13. Default Network Deactivations Are Correlated with Psychopathic Personality Traits

    PubMed Central

    Sheng, Tong; Gheytanchi, Anahita; Aziz-Zadeh, Lisa

    2010-01-01

    Background The posteromedial cortex (PMC) and medial prefrontal cortex (mPFC) are part of a network of brain regions that has been found to exhibit decreased activity during goal-oriented tasks. This network is thought to support a baseline of brain activity, and is commonly referred to as the “default network”. Although recent reports suggest that the PMC and mPFC are associated with affective, social, and self-referential processes, the relationship between these default network components and personality traits, especially those pertaining to social context, is poorly understood. Methodology/Principal Findings In the current investigation, we assessed the relationship between PMC and mPFC deactivations and psychopathic personality traits using fMRI and a self-report measure. We found that PMC deactivations predicted traits related to egocentricity and mPFC deactivations predicted traits related to decision-making. Conclusions/Significance These results suggest that the PMC and mPFC are associated with processes involving self-relevancy and affective decision-making, consistent with previous reports. More generally, these findings suggest a link between default network activity and personality traits. PMID:20830290

  14. Deactivation Mechanisms of Pt/Pd-based Diesel Oxidation Catalysts

    SciTech Connect

    Wiebenga, Michelle H.; Kim, Chang H.; Schmieg, Steven J.; Oh, Se H.; Brown, David B.; Kim, Do Heui; Lee, Jong H.; Peden, Charles HF

    2012-04-30

    Currently precious metal-based diesel oxidation catalysts (DOC) containing platinum (Pt) and palladium (Pd) are most commonly used for the oxidation of hydrocarbon and NO in diesel exhaust hydrocarbon oxidation. The present work has been carried out to investigate the deactivation mechanisms of the DOC from its real-world vehicle operation by coupling its catalytic activity measurements with surface characterization including x-ray diffraction, transmission electron microscopy, and x-ray photoelectron spectroscopy. A production Pt-Pd DOC was obtained after being aged on a vehicle driven for 135,000 miles in order to study its deactivation behavior. The performance of the vehicle-aged part was correlated with that of the simulated hydrothermal lab aged sample assuming that Pt-Pd sintering plays a major role in irreversible catalyst deactivation. In addition to the hydrothermal sintering, the deterioration of hydrocarbon and NO oxidation performance was caused by surface poisoning. The role of the various aging factors in determining long-term performance in mobile applications will be discussed.

  15. Gamification of Learning Deactivates the Default Mode Network.

    PubMed

    Howard-Jones, Paul A; Jay, Tim; Mason, Alice; Jones, Harvey

    2015-01-01

    We hypothesized that embedding educational learning in a game would improve learning outcomes, with increased engagement and recruitment of cognitive resources evidenced by increased activation of working memory network (WMN) and deactivation of default mode network (DMN) regions. In an fMRI study, we compared activity during periods of learning in three conditions that were increasingly game-like: Study-only (when periods of learning were followed by an exemplar question together with its correct answer), Self-quizzing (when periods of learning were followed by a multiple choice question in return for a fixed number of points) and Game-based (when, following each period of learning, participants competed with a peer to answer the question for escalating, uncertain rewards). DMN hubs deactivated as conditions became more game-like, alongside greater self-reported engagement and, in the Game-based condition, higher learning scores. These changes did not occur with any detectable increase in WMN activity. Additionally, ventral striatal activation was associated with responding to questions and receiving positive question feedback. Results support the significance of DMN deactivation for educational learning, and are aligned with recent evidence suggesting DMN and WMN activity may not always be anti-correlated. PMID:26779054

  16. Gamification of Learning Deactivates the Default Mode Network

    PubMed Central

    Howard-Jones, Paul A.; Jay, Tim; Mason, Alice; Jones, Harvey

    2016-01-01

    We hypothesized that embedding educational learning in a game would improve learning outcomes, with increased engagement and recruitment of cognitive resources evidenced by increased activation of working memory network (WMN) and deactivation of default mode network (DMN) regions. In an fMRI study, we compared activity during periods of learning in three conditions that were increasingly game-like: Study-only (when periods of learning were followed by an exemplar question together with its correct answer), Self-quizzing (when periods of learning were followed by a multiple choice question in return for a fixed number of points) and Game-based (when, following each period of learning, participants competed with a peer to answer the question for escalating, uncertain rewards). DMN hubs deactivated as conditions became more game-like, alongside greater self-reported engagement and, in the Game-based condition, higher learning scores. These changes did not occur with any detectable increase in WMN activity. Additionally, ventral striatal activation was associated with responding to questions and receiving positive question feedback. Results support the significance of DMN deactivation for educational learning, and are aligned with recent evidence suggesting DMN and WMN activity may not always be anti-correlated. PMID:26779054

  17. Deactivation of metastable single-crystal silicon hyperdoped with sulfur

    SciTech Connect

    Simmons, C. B.; Akey, Austin J.; Sullivan, Joseph T.; Buonassisi, Tonio; Krich, Jacob J.; Recht, Daniel; Aziz, Michael J.

    2013-12-28

    Silicon supersaturated with sulfur by ion implantation and pulsed laser melting exhibits broadband optical absorption of photons with energies less than silicon's band gap. However, this metastable, hyperdoped material loses its ability to absorb sub-band gap light after subsequent thermal treatment. We explore this deactivation process through optical absorption and electronic transport measurements of sulfur-hyperdoped silicon subject to anneals at a range of durations and temperatures. The deactivation process is well described by the Johnson-Mehl-Avrami-Kolmogorov framework for the diffusion-mediated transformation of a metastable supersaturated solid solution, and we find that this transformation is characterized by an apparent activation energy of E{sub A}=1.7 ± 0.1 eV. Using this activation energy, the evolution of the optical and electronic properties for all anneal duration-temperature combinations collapse onto distinct curves as a function of the extent of reaction. We provide a mechanistic interpretation of this deactivation based on short-range thermally activated atomic movements of the dopants to form sulfur complexes.

  18. Lignocellulosic hydrolysate inhibitors selectively inhibit/deactivate cellulase performance.

    PubMed

    Mhlongo, Sizwe I; den Haan, Riaan; Viljoen-Bloom, Marinda; van Zyl, Willem H

    2015-12-01

    In this study, we monitored the inhibition and deactivation effects of various compounds associated with lignocellulosic hydrolysates on individual and combinations of cellulases. Tannic acid representing polymeric lignin residues strongly inhibited cellobiohydrolase 1 (CBH1) and β-glucosidase 1 (BGL1), but had a moderate inhibitory effect on endoglucanase 2 (EG2). Individual monomeric lignin residues had little or no inhibitory effect on hydrolytic enzymes. However, coniferyl aldehyde and syringaldehyde substantially decreased the activity of CBH1 and deactivated BGL1. Acetic and formic acids also showed strong inhibition of BGL1 but not CBH1 and EG2, whereas tannic, acetic and formic acid strongly inhibited a combination of CBH1 and EG2 during Avicel hydrolysis. Diminishing enzymatic hydrolysis is largely a function of inhibitor concentration and the enzyme-inhibitor relationship, rather than contact time during the hydrolysis process (i.e. deactivation). This suggests that decreased rates of hydrolysis during the enzymatic depolymerisation of lignocellulosic hydrolysates may be imparted by other factors related to substrate crystallinity and accessibility. PMID:26453468

  19. Preclosure radiological safety analysis for the exploratory shaft facilities; Yucca Mountain Site Characterization Project

    SciTech Connect

    Ma, C.W.; Miller, D.D.; Jardine, L.J.

    1992-06-01

    This study assesses which structures, systems, and components of the exploratory shaft facility (ESF) are important to safety when the ESF is converted to become part of the operating waste repository. The assessment follows the methodology required by DOE Procedure AP-6.10Q. Failures of the converted ESF during the preclosure period have been evaluated, along with other underground accidents, to determine the potential offsite radiation doses and associated probabilities. The assessment indicates that failures of the ESF will not result in radiation doses greater than 0.5 rem at the nearest unrestricted area boundary. Furthermore, credible accidents in other underground facilities will not result in radiation doses larger than 0.5 rem, even if any structure, system, or component of the converted ESF fails at the same time. Therefore, no structure, system, or component of the converted ESF is important to safety.

  20. Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Master Equipment List

    SciTech Connect

    IRWIN, J.J.

    1999-09-21

    This document provides the master equipment list (MEL) for the Cold Vacuum Drying Facility (CVDF). The MEL was prepared to comply with DOE Standard 3024-98, Content of System Design Descriptions. The MEL was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems and the CVDF System Design Descriptions (SDD). The MEL identifies the SSCs and their safety functions, the design criteria, codes and standards, and quality assurance requirements that are required for establishing the safety design basis of the SSCs. The MEL also includes operating parameters, manufacturer information, and references the procurement specifications for the SSCs. This MEL shall be updated, expanded, and revised in accordance with future phases of the CVDF SAR, the SDD's, and CVDF operations.

  1. The CELSS Test Facility Project - An example of a CELSS flight experiment system

    NASA Technical Reports Server (NTRS)

    Macelroy, R. D.; Straight, C. L.

    1992-01-01

    The design of the facility is described in terms of its use as an investigation tool for evaluating crop growth in space with reference to required emerging technologies. NASA's CELSS Test Facility (CTF) is designed to permit the measurement of crop-plant productivity under microgravity conditions including biomass production, food production, water transpiration, and O2/CO2 exchanges. Crucial hardware tests and qualifications are identified to assure the operation of CTF technologies in space including the nutrient-delivery, water-condensation, and gas-liquid-mixing subsystems. The design concept and related scientific requirements are described and shown to provide microgravity crop research. The CTF is expected to provide data for plant research and for concepts for bioregenerative life-support systems for applications to Martian, lunar, and space-station missions.

  2. Spent Nuclear Fuel Project path forward: nuclear safety equivalency to comparable NRC-licensed facilities

    SciTech Connect

    Garvin, L.J.

    1995-11-01

    This document includes the Technical requirements which meet the nuclear safety objectives of the NRC regulations for fuel treatment and storage facilities. These include requirements regarding radiation exposure limits, safety analysis, design and construction. This document also includes administrative requirements which meet the objectives of the major elements of the NRC licensing process. These include formally documented design and safety analysis, independent technical review, and oppportunity for public involvement.

  3. Supplemental design requirements document, Multifunction Waste Tank Facility, Project W-236A. Revision 1

    SciTech Connect

    Groth, B.D.

    1995-01-11

    The Multi-Function Waste Tank Facility (MWTF) consists of four, nominal 1 million gallon, underground double-shell tanks, located in the 200-East area, and two tanks of the same capacity in the 200-West area. MWTF will provide environmentally safe storage capacity for wastes generated during remediation/retrieval activities of existing waste storage tanks. This document delineates in detail the information to be used for effective implementation of the Functional Design Criteria requirements.

  4. C.2 analysis of the environmental effects of the Nuclear Facilities Modernization project

    SciTech Connect

    1991-04-01

    This analysis indicates that the potential impacts associated with the current/projected Mound tritium operations are adequately bounded by the existing environmental impacts analyzed in the FEIS. It also indicates that the incremental impacts of the NFM project will make a positive contribution to the overall impact of current/projected tritium operations. Except for minor and normal temporary conditions during the construction and demolition phases, the NFM project would measurably reduce the likelihood of adverse consequences to the environment. Relocation of the PE/PD laboratory operations from the SW/R Tritium Complex to the T Building will place these operations in a safer, state-of-the-art glovebox systems. Through the utilization of modern laboratory equipment and enhanced containment, the project will reduce the quantity of routine airborne tritium releases and volume of solid tritiated wastes resulting from routine PE/PD laboratory operations. The increased reliance placed on engineered safety aspects and stronger mitigative measures by the project will also reduce the risk associated with these operations by reducing both the probability and consequences of unusual occurrences involving uncontrolled tritium releases.

  5. Construction of a naturally occurring radioactive material project in the BeAAT hazardous waste facilities.

    PubMed

    Abuahmad, H

    2015-06-01

    This paper does not necessarily reflect the views of the International Commission on Radiological Protection. Naturally occurring radioactive material (NORM) is produced during exploration and production operations of subsidiaries of the Abu Dhabi National Oil Company (ADNOC) in the United Arab Emirates, and accumulates in drilling tubulars, plant equipment, and components. These NORM hazardous wastes need to be managed in such a way that they do not damage human health and the environment. The primary radionuclides of concern in the oil and gas industries are radium-226 and radium-228. These radioisotopes are the decay products of uranium and thorium isotopes that are present in subsurface formations from which hydrocarbons are produced. While uranium and thorium are largely immobile, radium is slightly more soluble and may become mobilised in the fluid phases of the formation (International Association of Oil & Gas Producers, 2008). In order to treat and dispose of NORM waste products safely, ADNOC's subsidiary 'TAKREER' is developing a new facility, on behalf of all ADNOC subsidiaries, within the existing Central Environmental Protection Facilities (BeAAT) in Ruwais city. The NORM plant is envisaged to treat, handle, and dispose of NORM waste in the forms of scale, sludge, and contaminated equipment. The NORM treatment facility will cover activities such as decontamination, volume reduction, NORM handling, and concrete immobilisation of NORM waste into packages for designated landfilling. PMID:25816275

  6. The new Arecibo Observatory Remote Optical Facility (AO-ROF) in Culebra Island, Puerto Rico: Current Status and Future Projects

    NASA Astrophysics Data System (ADS)

    Santos, P. T.

    2015-12-01

    The idea of establishing the Arecibo Observatory Remote Optical Facility (AO-ROF) in the island of Culebra is a solution to mitigate the ever cumulative quantity of cloud, fog, and rain that has distressed observations at the Arecibo Observatory (AO) during major optical campaigns and observations. Given Culebra Island's favorable geographical and climatological characteristics as its low elevation and geographic location, it appears to have more steady weather conditions than Arecibo, so therefore it provides more availability for optical observations. Placed on Culebra, optical instruments can observe the same thermospheric volume over AO sampled by the Incoherent Scatter Radar (ISR). This capability will become especially important during the High Frequency (HF) facility is on operation. Small and large scale irregularities created by that HF can be readily observed and tracked from the Culebra site, and simultaneous observations from AO of the same atmospheric volume will permit direct vector measurements of dynamical evolution of the irregularities. This work presents a discussion of the current status of AO-ROF facility, as well the future projects.

  7. A Client-Centered Community Engagement Project: Improving the Health and Wellness of Older Adults in an Assisted Living Facility.

    PubMed

    Ballantyne-Rice, Madeleine; Chopp, Kayla; Evans, Lisa; Ho, Vanessa; Hsiung, Wan Ping; Simon, Marian Alexandra; Wu, Kaiyu; Donnelly, Tam Truong

    2016-08-01

    Central to nursing practice is the promotion of health and wellness practices. Drawing on the Community as Partner Model, nursing process, Nursing Interventions Classification, and Logic Model, second-year nursing students collaborated with staff and residents of an assisted living facility to promote health and wellness in the older adult population. Windshield surveys, resident surveys, key informant interviews, and focus group interviews were conducted to gain insight into the perceptions and experiences of staff and residents. The majority of residents indicated they were satisfied with life at the facility and their needs have been adequately met. Strengths and areas for improvement were identified in several aspects, including the facility atmosphere and location, quality of staff and health care services, recreational and dietary services, and social support networks. By partnering with community key stakeholders, valuing all different perspectives, and connecting theory to practice, a successful client-centered community clinical project was demonstrated. [Journal of Gerontological Nursing, 42(8), 44-51.]. PMID:27263539

  8. Cost Estimating for Decommissioning of a Plutonium Facility--Lessons Learned From The Rocky Flats Building 771 Project

    SciTech Connect

    Stevens, J. L.; Titus, R.; Sanford, P. C.

    2002-02-26

    The Rocky Flats Closure Site is implementing an aggressive approach in an attempt to complete Site closure by 2006. The replanning effort to meet this goal required that the life-cycle decommissioning effort for the Site and for the major individual facilities be reexamined in detail. As part of the overall effort, the cost estimate for the Building 771 decommissioning project was revised to incorporate both actual cost data from a recently-completed similar project and detailed planning for all activities. This paper provides a brief overview of the replanning process and the original estimate, and then discusses the modifications to that estimate to reflect new data, methods, and planning rigor. It provides the new work breakdown structure and discusses the reasons for the final arrangement chosen. It follows with the process used to assign scope, cost, and schedule elements within the new structure, and development of the new code of accounts. Finally, it describes the project control methodology used to track the project, and provides lessons learned on cost tracking in the decommissioning environment.

  9. PEGASUS, a European research project on the effects of gas in underground storage facilities for radioactive waste

    SciTech Connect

    Haijtink, B.; McMenamin, T.

    1993-12-31

    Whereas the subject of gas generation and possible gas release from radioactive waste repositories has gained in interest on the international scene, the Commission of the European Communities has increased its research efforts on this issue. In particular in the 4th five year R and D program on Management and Storage of Radioactive Waste (1990--1994), a framework has been set up in which research efforts on the subject of gas generation and migration, supported by the CEC, are brought together and coordinated. In this project, called PEGASUS, Project on the Effects of GAS in Underground Storage facilities for radioactive waste, about 20 organizations and research institutes from 7 European countries are involved. The project covers both experimental and theoretical studies of the processes of gas formation and possible gas release from the different waste types, LLW, ILW and HLW, under typical repository conditions in suitable geological formations as clay, salt and granite. In this paper an overview is given of the various studies undertaken in the project as well as some first results presented.

  10. M.U.S.T. 2007 Summer Research Project at NASA's KSC MILA Facility

    NASA Technical Reports Server (NTRS)

    PintoRey, Christian R.

    2007-01-01

    The summer research activity at Kennedy Space Center (KSC) aims to introduce the student to the basic principles in their field of study. While at KSC, a specific research project awaits the student to complete. As an Aeronautical Engineering student, my assigned project is to assist the cognizant engineer, Mr. Troy Hamilton, in the six engineering phases for replacing the Ponce De Leon (PDL)4.3M Antenna Control Unit (ACU). Although the project mainly requires the attention of two engineers and two students, it also involves the participation of many colleagues at various points during the course of the engineering change (EC). Since the PDL 4.3M ACU engineering change makes both hardware and software changes, it calls upon the expertise of a Hardware Engineer as well as a Software Engineer. As students, Mr. Jeremy Bresette and I have worked side by side with the engineers, gaining invaluable experience. We work in two teams, the hardware team and the software team, On certain tasks, we assist the engineers, while on others we assume their roles. By diligently working in this fashion, we are learning how to communicate effectively as professionals, despite the fact that we are studying different engineering fields. This project has been a great fit for my field of study, as it has highly improved my awareness of the many critical tasks involved in carrying out an engineering project.

  11. Site Studies for the SuperB Collider and Synchrotron Radiation Facility Project

    SciTech Connect

    Tomassini, S.; Biagini, M.E.; Raimondi, P.; Sanelli, C.; Bolzon, B.; Deleglise, G.; Jeremie, A.; Seeman, J.; /SLAC

    2012-04-26

    The SuperB complex project aims at the construction of a very high luminosity (10{sup 36} cm{sup -2}s{sup -1}) asymmetric e{sup +}e{sup -} B-factory and a few X-ray synchrotron beam lines (SR). The project has been recently approved by the Italian Government as part of the National Research Plan. The Tor Vergata University location has been chosen and a Consortium among INFN, University of Rome II Tor Vergata and the Research Ministry is being signed, allowing for the constitution of the 'Cabibbo Laboratory', where the SuperB project will be hosted. This paper presents and describes the status of the preliminary design of the site layout, related issues for the chosen site and the preliminary ground motion (GM) measurement results.

  12. Determination of the Microbial Diversity of Spacecraft Assembly Facilities: First Results of the Project MiDiv

    NASA Astrophysics Data System (ADS)

    Rettberg, P.; Horneck, G.; Fritze, D.; Stackebrandt, E.; Kminek, G.

    The first step in the implementation of planetary protection guidelines encompasses a qualitative and quantitative inventory of the bioburden of spacecraft assembly facilities. In such an artificial environment mainly microorganisms are to be expected that are brought in by the humans themselves and that are able to withstand the controlled air circulation, the low relative humidity, the moderately high temperature and the low-nutrient conditions in the clean rooms of the assembly facilities. With informations about the composition of these microbial communities the development and/or optimization of adequate cleaning and sterilization procedures for spacecraft preparation before launch will be possible. The bioburden assessment in spacecraft assembly facilities requires a standardized procedure for sampling the air and surfaces in the facilities as well as of the spacecraft, a transfer of the biological samples under controlled conditions to the analyzing laboratory and a scientifically approved set of methods for analysis. In the ESA project MiDiv we started to investigate the bioburden of spacecrafts using the satellites SMART-1 and ROSETTA as test objects. The analysis of the samples included so far cultivation on different media at different pH and temperatures with and without oxygen with and without pasteurization, establishment of a culture collection of bacteria and partial 16S rRNA gene analysis. The results of these preliminary measurements, the total number of microorganisms, the numbers of colony forming units, differentiated according to the subgroups of aerobes, facultative anaerobes and anaerobes, and the phylogenetic classification, will be assessed with respect to the physiological potential of the identified microorganisms to withstand the different cleaning and sterilizing procedures used up to now for planetary protection measures. In the next step the ability of selected microorganisms to survive has to tested under environmental conditions as

  13. LLNL heart valve condition classification project anechoic testing results at the TRANSDEC evaluation facility

    SciTech Connect

    Candy, J V

    1999-10-31

    This report first briefly outlines the procedures and support/activation fixture developed at LLNL to perform the heart valve tests in an anechoic-like tank at the US Navy Transducer Evaluation Facility (TransDec) located in San Diego, CA. Next they discuss the basic experiments performed and the corresponding experimental plan employed to gather meaningful data systematically. The signal processing required to extract the desired information is briefly developed along with some of the data. Finally, they show the results of the individual runs for each valve, point out any of the meaningful features and summaries.

  14. State waste discharge permit application: 200 Area Treated Effluent Disposal Facility (Project W-049H)

    SciTech Connect

    Not Available

    1994-08-01

    As part of the original Hanford Federal Facility Agreement and Concent Order negotiations, US DOE, US EPA and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground to the Hanford Site are subject to permitting in the State Waste Discharge Permit Program (SWDP). This document constitutes the SWDP Application for the 200 Area TEDF stream which includes the following streams discharged into the area: Plutonium Finishing Plant waste water; 222-S laboratory Complex waste water; T Plant waste water; 284-W Power Plant waste water; PUREX chemical Sewer; B Plant chemical sewer, process condensate, steam condensate; 242-A-81 Water Services waste water.

  15. A student design project to improve power quality for a commercial facility

    SciTech Connect

    Lentz, R.C.; Mercede, F.J.; Mercede, J.N. Jr.

    1995-02-01

    A recent paper reported on the success of industry-sponsored student projects to promote power quality education. One such project, sponsored by BCM Engineers in Plymouth Meeting, PA, was entitled Power Quality Survey of a Commercial System. The results of the survey confirmed the suspicion that power line disturbances (i.e., normal-mode and common-mode impulses and noise) were responsible for the outages, premature failures and data communication errors of critical microprocessor-based equipment (e.g., terminals, workstations, network file servers, teleconferencing video equipment, etc.). As a follow-up to this project, this paper reports on the results of a student design project to develop a cost-effective implementation plan to mitigate the causes of the BCM power quality problems (i.e., grounding, wiring methods, load configurations, surge protection, and employee practices). Since BCM only leases several floors of the commercial building, it was important that the design be cost-effective and unobtrusive to the other tenants in the building. The design presented is simple and effective, and it conforms to the NEC{reg_sign} and accepted industry practice.

  16. 75 FR 877 - Cancellation of the South Valley Facilities Expansion Project-Clark County, NV

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-06

    ... (SVFE) Project, published in the Federal Register on April 18, 2008 (73 FR 21155). FOR FURTHER... Bureau of Reclamation, Lower Colorado Region, P.O. Box 61470, Boulder City, NV 89006-1470. SUPPLEMENTARY..., 2009. Lorri Gray-Lee, Regional Director, Lower Colorado Region. BILLING CODE 4310-MN-P...

  17. School Construction and Normalization. RAS Project: Research in Educational Facilities. A Report.

    ERIC Educational Resources Information Center

    Corriveau, Gerard-A.

    This document reports the development of a system of mass-produced standardized components for school construction. The project was originated and implemented to solve a problem connected with the heavy demand for schools that confronted the Montreal Catholic School Board. The report outlines the problem -- a need for schools -- and gives details…

  18. Spent nuclear fuel project cold vacuum drying facility safety equipment list

    SciTech Connect

    IRWIN, J.J.

    1999-02-24

    This document provides the safety equipment list (SEL) for the Cold Vacuum Drying Facility (CVDF). The SEL was prepared in accordance with the procedure for safety structures, systems, and components (SSCs) in HNF-PRO-516, ''Safety Structures, Systems, and Components,'' Revision 0 and HNF-PRO-097, Engineering Design and Evaluation, Revision 0. The SEL was developed in conjunction with HNF-SO-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998). The SEL identifies the SSCs and their safety functions, the design basis accidents for which they are required to perform, the design criteria, codes and standards, and quality assurance requirements that are required for establishing the safety design basis of the SSCs. This SEL has been developed for the CVDF Phase 2 Safety Analysis Report (SAR) and shall be updated, expanded, and revised in accordance with future phases of the CVDF SAR until the CVDF final SAR is approved.

  19. The PixFEL project: Progress towards a fine pitch X-ray imaging camera for next generation FEL facilities

    NASA Astrophysics Data System (ADS)

    Rizzo, G.; Batignani, G.; Benkechkache, M. A.; Bettarini, S.; Casarosa, G.; Comotti, D.; Dalla Betta, G.-F.; Fabris, L.; Forti, F.; Grassi, M.; Lodola, L.; Malcovati, P.; Manghisoni, M.; Mendicino, R.; Morsani, F.; Paladino, A.; Pancheri, L.; Paoloni, E.; Ratti, L.; Re, V.; Traversi, G.; Vacchi, C.; Verzellesi, G.; Xu, H.

    2016-07-01

    The INFN PixFEL project is developing the fundamental building blocks for a large area X-ray imaging camera to be deployed at next generation free electron laser (FEL) facilities with unprecedented intensity. Improvement in performance beyond the state of art in imaging instrumentation will be explored adopting advanced technologies like active edge sensors, a 65 nm node CMOS process and vertical integration. These are the key ingredients of the PixFEL project to realize a seamless large area focal plane instrument composed by a matrix of multilayer four-side buttable tiles. In order to minimize the dead area and reduce ambiguities in image reconstruction, a fine pitch active edge thick sensor is being optimized to cope with very high intensity photon flux, up to 104 photons per pixel, in the range from 1 to 10 keV. A low noise analog front-end channel with this wide dynamic range and a novel dynamic compression feature, together with a low power 10 bit analog to digital conversion up to 5 MHz, has been realized in a 110 μm pitch with a 65 nm CMOS process. Vertical interconnection of two CMOS tiers will be also explored in the future to build a four-side buttable readout chip with high density memories. In the long run the objective of the PixFEL project is to build a flexible X-ray imaging camera for operation both in burst mode, like at the European X-FEL, or in continuous mode with the high frame rates anticipated for future FEL facilities.

  20. Recent performance results of the National Ignition Facility Beamlet demonstration project

    SciTech Connect

    Van Wonterghem, B.M.; Wegner, P.J.; Lawson, J.K.; Auerbach, J.M.; Henesian, M.A.; Barker, C.E.; Thompson, C.E.; Widmayer, C.C.; Caird, J.A.

    1996-08-01

    The laser driver for the National Ignition Facility will be a departure from previous inertial confinement fusion laser architecture of a master oscillator single pass power amplifier (MOPA) design. The laser will use multi-segment Nd:Glass amplifiers in a multipass cavity arrangement, which can be assembled into compact and cost effective arrays to deliver the required multi- megajoule energy to target. A single beam physics prototype, the Beamlet, has been in operation for over two years and has demonstrated the feasibility of this architecture. We present a short review of Beamlet`s performance and limitations based on beam quality both at its fundamental and frequency converted wavelengths of 1.053 and 0.351 {mu}m.

  1. Mixed and low-level waste treatment facility project. Volume 3, Waste treatment technologies (Draft)

    SciTech Connect

    Not Available

    1992-04-01

    The technology information provided in this report is only the first step toward the identification and selection of process systems that may be recommended for a proposed mixed and low-level waste treatment facility. More specific information on each technology will be required to conduct the system and equipment tradeoff studies that will follow these preengineering studies. For example, capacity, maintainability, reliability, cost, applicability to specific waste streams, and technology availability must be further defined. This report does not currently contain all needed information; however, all major technologies considered to be potentially applicable to the treatment of mixed and low-level waste are identified and described herein. Future reports will seek to improve the depth of information on technologies.

  2. The CELSS Test Facility project: an example of a CELSS flight experiment system.

    PubMed

    MacElroy, R D; Straight, C L

    1992-01-01

    The CELSS Test Facility (CTF) is a device for measuring crop plant productivity in the micro-gravity environment of Space Station Freedom. It will allow us to address questions of crop productivity in space, versus that on the ground. The crop productivity factors that will be measured are rates of: 1) biomass production, 2) food production, 3) O2 and CO2 exchange, and 4) water transpiration. In addition, other productivity factors of specific crops will be determined, such as : 1) the ratio of edible to inedible biomass (harvest index), 2) leaf area exposed to and collecting light (leaf area index), 3) ratio of root mass to total biomass, and 4) photosynthetic efficiency (ratio of moles of CO2 fixed (or O2 produced), per mole of photons of specific energies used). Plant and crop morphology, at several levels, ranging from the community to the sub-cellular, will also be evaluated. PMID:11537082

  3. Activation and deactivation of high concentration arsenic with some evidence of precipitation

    SciTech Connect

    Rousseau, P.M.; Griffin, P.B.; Plummer, J.D.; Carey, P.G.

    1992-12-29

    Using box-shaped profiles created by laser melt annealing, the authors investigate the kinetics of arsenic activation and deactivation. They find deactivation shows no history effects, which can be consistent either with clustering or precipitation for the cases considered. For activation, they notice it occurs on very short time scales, followed by a slower deactivation process. This is suggestive evidence that at least some precipitation occurs.

  4. Diesel emissions and ventilation exhaust sampling in the North Ramp of the Yucca Mountain Project Exploratory Studies Facility

    SciTech Connect

    George, J.T.

    1995-11-01

    A series of ventilation experiments have been performed to assess the potential retention of diesel exhaust constituents in the North Ramp of the Yucca Mountain Site Characterization Project`s Exploratory Studies Facility (ESF). Measurements were taken to help evaluate the potential impact of retained diesel exhaust constituents on future in-situ experiments and long-term waste isolation. Assessment of the diesel exhaust retention in the ESF North Ramp required the measurement of air velocities, meteorological measurements, quantification of exhaust constituents within the ventilation air stream, multiple gas sample collections, and on-line diesel exhaust measurements. In order to assess variability within specific measurements, the experiment was divided into three separate sampling events. Although somewhat variable from event to event, collected data appear to support pre-test assumptions of high retention rates for exhaust constituents within the tunnel. The results also show that complete air exchange in the ESF does not occur within the estimated 16 to 20 minutes derived from the ventilation flowrate measurements. Because the scope of work for these activities covered only measurement and acquisition of data, no judgment is offered by the author as to the implications of this work. Final analyses and decisions based upon the entire compendium of data associated with this investigation is being undertaken by the Repository and ESF Ventilation Design Groups of the Yucca Mountain Site Characterization Project.

  5. RH-LLW Disposal Facility Project CD-2/3 to Design/Build Proposal Reconciliation Report

    SciTech Connect

    Annette L. Schafer

    2012-06-01

    A reconciliation plan was developed and implemented to address potential gaps and responses to gaps between the design/build vendor proposals and the Critical Decision-2/3 approval request package for the Remote-Handled Low Level Waste Disposal Facility Project. The plan and results of the plan implementation included development of a reconciliation team comprised of subject matter experts from Battelle Energy Alliance and the Department of Energy Idaho Operations Office, identification of reconciliation questions, reconciliation by the team, identification of unresolved/remaining issues, and identification of follow-up actions and subsequent approvals of responses. The plan addressed the potential for gaps to exist in the following areas: • Department of Energy Order 435.1, “Radioactive Waste Management,” requirements, including the performance assessment, composite analysis, monitoring plan, performance assessment/composite analysis maintenance plan, and closure plan • Environmental assessment supporting the National Environmental Policy Act • Nuclear safety • Safeguards and security • Emplacement operations • Requirements for commissioning • General project implementation. The reconciliation plan and results of the plan implementation are provided in a business-sensitive project file. This report provides the reconciliation plan and non-business sensitive summary responses to identified gaps.

  6. [Educational Facilities for Pregnant School-Age Girls in Districts 3, 4, 12, 13, and 18. Project No. 1369. Evaluation of ESEA Title I Projects in New York City 1968-69.

    ERIC Educational Resources Information Center

    Appel, Yetta; Berken, Ruth R.

    This project for pregnant school age girls is an ESEA Title I program operating in five facilities in Manhattan, Bronx, and Brooklyn. The primary objective of the project was to assist pregnant school age girls complete their education by being able to attend school. Additional objectives included provision of information and training in personal…

  7. Advanced Instrumentation, Information and Control (II&C) Research and Development Facility Buildout and Project Execution of LWRS II&C Pilot Projects 1 and 3

    SciTech Connect

    Ronald Farris; Johanna Oxstrand; Gregory Weatherby

    2011-09-01

    The U.S. Department of Energy (DOE) is sponsoring research, development, and deployment on light water reactor sustainability (LWRS), in which the Idaho National Laboratory (INL) is working closely with nuclear utilities to develop technologies and solutions to help ensure the safe operational life extension of current reactors. As technologies are introduced that change the operation of the plant, the LWRS pilot projects can help identify their best-advanced uses and help demonstrate the safety of these technologies. In early testing of operator performance given these emerging technologies will ensure the safety and usability of systems prior to large-scale deployment and costly verification and validation at the plant. The aim of these collaborations, demonstrations, and approaches are intended to lessen the inertia that sustains the current status quo of today's II&C systems technology, and to motivate transformational change and a shift in strategy to a long-term approach to II&C modernization that is more sustainable. Research being conducted under Pilot Project 1 regards understanding the conditions and behaviors that can be modified, either through process improvements and/or technology deployment, to improve the overall safety and efficiency of outage control at nuclear facilities. The key component of the research in this pilot project is accessing the delivery of information that will allow researchers to simulate the control room, outage control center (OCC) information, and plant status data. The simulation also allows researchers to identify areas of opportunity where plant operating status and outage activities can be analyzed to increase overall plant efficiency. For Pilot Project 3 the desire is to demonstrate the ability of technology deployment and the subsequent impact on maximizing the 'Collective Situational Awareness' of the various stakeholders in a commercial nuclear power plant. Specifically, the desire is to show positive results in plant

  8. Reoxidation and deactivation of supported cobalt Fischer-Tropsch catalysts

    SciTech Connect

    Schanke, D.; Hilmen, A.M.; Bergene, E.

    1995-12-01

    The Fischer-Tropsch synthesis is an attractive possibility for conversion of natural gas into high quality liquid fuels. Due to its low water-gas shift activity, good activity/selectivity properties and relatively low price, cobalt is the choice of catalytic metal for natural gas conversion via Fischer-Tropsch synthesis. In the cobalt-catalyzed Fischer-Tropsch reaction, oxygen is mainly rejected as water. In this paper we describe the influence of water on supported cobalt catalysts. The deactivation of supported Co catalysts was studied in a fixed-bed reactor using synthesis gas feeds containing varying concentrations of water vapour.

  9. Deactivation of slurry phase Fischer-Tropsch catalysts

    SciTech Connect

    Gormley, R.J.; Zarochak, M.F.; Deffenbaugh, P.W.; Rao, K.R.P.M.

    1996-12-31

    The influence of the liquid medium on Fischer-Tropsch (F-T) chemistry has received only minimal attention in the literature. The focus of this investigation was to determine the impact of the liquid starting medium on syngas (H{sub 2}+CO) conversion in a 1-liter CSTR. The results of the work indicate a greater deactivation rate for the F-T reaction in heavier starting media, average carbon number {ge}48, versus a medium with an average carbon number of 28.

  10. Mechanisms of amplification, deactivation, and noise reduction in invertebrate photoreceptors.

    PubMed

    Lisman, J; Erickson, M A; Richard, E A; Cote, R H; Bacigalupo, J; Johnson, E; Kirkwood, A

    1992-01-01

    In this review we have discussed the problem of deactivation at both the rhodopsin and G protein levels. Of particular interest is the novel observation that rhodopsin deactivation can be modulated by light. This modulation is likely to play an important role in light adaptation by reducing the gain of transduction. One interesting possibility is that this modulation involves the phosphorylation of an arrestin-like molecule, but this remains to be tested. One of the experimental advantages of Limulus photoreceptors is the large size of the single photon responses and the fact that even single G proteins produce a detectable response. This made possible the observation that nonhydrolyzable GTP analogues produce discrete transient events rather than the step-like events that would be predicted by previous models. This observation led us to a new view of how enzyme deactivation is coupled to GTP hydrolysis on G protein. According to this view, enzymes are activated by G protein, but can be deactivated by processes that are not dependent on G protein or the hydrolysis of GTP. We have conducted several types of experiments, including some on the vertebrate rod system, that strongly support this hypothesis. A second major theme of this review is transduction noise. The available biochemical evidence suggests that both G protein and G protein-activated enzymes are likely to become spontaneously active and generate undesirable noise. Our measurements indicate, however, that this noise is orders of magnitude smaller than would be predicted by simple models, suggesting that special mechanisms must exist for suppressing this noise. We have proposed a specific mechanism by which enzymes regulated allosterically by multiple subunits could act as coincidence detectors to reduce transduction noise. Finally, there is the fundamental question of which second messengers have a direct role in invertebrate phototransduction. After Fesenko et al. (1985) showed that the light

  11. Rupture loop annex ion exchange RLAIX vault deactivation

    SciTech Connect

    Ham, J.E.; Harris, D.L., Westinghouse Hanford

    1996-08-01

    This engineering report documents the deactivation, stabilization and final conditions of the Rupture Loop Annex Ion Exchange (RLAIX) Vault located northwest of the 309 Building`s Plutonium Recycle Test Reactor (PRTR). Twelve ion exchange columns, piping debris, and column liquid were removed from the vault, packaged and shipped for disposal. The vault walls and floor were decontaminated, and portions of the vault were painted to fix loose contamination. Process piping and drains were plugged, and the cover blocks and rain cover were installed. Upon closure,the vault was empty, stabilized, isolated.

  12. Solid-state enzyme deactivation in air and in organic solvents

    SciTech Connect

    Toscano, G.; Pirozzi, D.; Maremonti, M.; Greco, G. Jr. . Dipartimento di Ingegneria Chimica)

    1994-09-05

    Thermal deactivation of solid-state acid phosphatase is analyzed, both in the presence and in the absence of organic solvents. The thermal deactivation profile departs from first order kinetics and shows an unusual, temperature-dependent, asymptotic value of residual activity. The process is described by a phenomenological equation, whose theoretical implications are also discussed. The total amount of buffer salts in the enzyme powder dramatically affects enzyme stability in the range 70 to 105 C. The higher salt/protein ratio increases the rate of thermal deactivation. The deactivation rate is virtually unaffected by the presence of organic solvents, independent of their hydrophilicity.

  13. “That’s Like an Act of Suicide” Patients’ Attitudes Toward Deactivation of Implantable Defibrillators

    PubMed Central

    Mehta, Davendra; Siddiqui, Saima; Teitelbaum, Ezra; Zeidman, Jessica; Singson, Magdelena; Pe, Elena; Bradley, Elizabeth H.; Morrison, R. Sean

    2007-01-01

    Objective To understand potential patient barriers to discussions about implantable cardioverter defibrillator (ICD) deactivation in patients with advanced illness. Design Qualitative focus groups. Participants Fifteen community-dwelling, ambulatory patients with ICDs assigned to focus groups based on duration of time since implantation and whether they had ever received a shock from their device. Approach A physician and a social worker used a predetermined discussion guide to moderate the groups, and each session was audiotaped and subsequently transcribed. Transcripts were analyzed using the method of constant comparison. Results No participant had ever discussed deactivation with their physician nor knew that deactivation was an option. Patients expressed a great deal of anxiety about receiving shocks from their device. Participants discussed why they needed the device and expressed desire for more information about the device; however, they would not engage in conversations about deactivating the ICD. One patient described deactivation “like an act of suicide” and all patients believed that the device was exclusively beneficial. Patients also expressed a desire to have their physician make the decision about deactivation. Conclusions None of the patients in our study knew that they might need to deactivate their ICD as their health worsens. These community-dwelling outpatients were not willing to discuss the issue of ICD deactivation and their attitudes about deactivation might impede patients from engaging in these conversations. These findings are in contrast to findings in other advance care planning research and may be related to the unique nature of the ICD. PMID:18095037

  14. Weldon Spring Site Remedial Action Project Federal Facilities Agreement: Quarterly environmental data summary for third quarter 1998

    SciTech Connect

    1998-11-06

    In support of the Weldon Spring Site Remedial Action Project Federal Facilities Agreement, a copy of the Quarterly Environmental Data Summary (QEDS) for the third quarter of 1998 is enclosed. The data presented in this letter and attachment constitute the QEDS. The data, except for air monitoring data and site KPA generated data (uranium analyses), were received from the contract laboratories, verified by the Weldon Spring Site verification group, and merged into the database during the third quarter of 1998. Air monitoring data presented are the most recent complete sets of quarterly data. Significant data, defined as data values that have exceeded defined above normal Level 2 values, are discussed in this letter for Environmental Monitoring Plan (EMP) generated data only. Above normal Level 2 values are based, in ES and H procedures, on historical high values, DOE Derived Concentration Guides (DCGs), NPDES limits, and other guidelines. The procedures also establish actions to be taken in the event that above normal data occur.

  15. Geotechnical characterization of the North Ramp of the Exploratory Studies Facility: Yucca Mountain Site Characterization Project. Volume 1, Data summary

    SciTech Connect

    Brechtel, C.E.; Lin, Ming; Martin, E.; Kessel, D.S.

    1995-05-01

    This report presents the results of geological and geotechnical characterization of the Miocene volcanic tuff rocks of the Timber Mountain and Paintbrush groups that the tunnel boring machine will encounter during excavation of the Exploratory Studies Facility (ESF) North Ramp. The is being constructed by the DOE as part of the Yucca Mountain Project site characterization activities. The purpose of these activities is to evaluate the feasibility of locating a potential high-level nuclear waste repository on lands adjacent to the Nevada Test Site, Nye County, Nevada. This report was prepared as part of the Soil and Rock Properties Studies in accordance with the 8.3.1.14.2 Study Plan. This report is volume 1 of the data summary.

  16. Solidification under zero gravity: A Long Duration Exposure Facility (LDEF) experiment for an early space shuttle mission. [project planning

    NASA Technical Reports Server (NTRS)

    Bailey, J. A.

    1976-01-01

    Project planning for two series of simple experiments on the effect of zero gravity on the melting and freezing of metals and nonmetals is described. The experiments will be performed in the Long Duration Exposure Facility, and their purpose will be to study: (1) the general morphology of metals and nonmetals during solidification, (2) the location of ullage space (liquid-vapor interfaces), and (3) the magnitude of surface tension driven convection during solidification of metals and nonmetals. The preliminary design of the experiments is presented. Details of the investigative approach, experimental procedure, experimental hardware, data reduction and analysis, and anticipated results are given. In addition a work plan and cost analysis are provided.

  17. Characterisation of mixed neutron photon workplace fields at nuclear facilities by spectrometry (energy and direction) within the EVIDOS project.

    PubMed

    Luszik-Bhadra, M; Bartlett, D; Bolognese-Milsztajn, T; Boschung, M; Coeck, M; Curzio, G; d'Errico, F; Fiechtner, A; Lacoste, V; Lindborg, L; Reginatto, M; Schuhmacher, H; Tanner, R; Vanhavere, F

    2007-01-01

    Within the EC project EVIDOS, 17 different mixed neutron-photon workplace fields at nuclear facilities (boiling water reactor, pressurised water reactor, research reactor, fuel processing, storage of spent fuel) were characterised using conventional Bonner sphere spectrometry and newly developed direction spectrometers. The results of the analysis, using Bayesian parameter estimation methods and different unfolding codes, some of them especially adapted to simultaneously unfold energy and direction distributions of the neutron fluence, showed that neutron spectra differed strongly at the different places, both in energy and direction distribution. The implication of the results for the determination of reference values for radiation protection quantities (ambient dose equivalent, personal dose equivalent and effective dose) and the related uncertainties are discussed. PMID:17890781

  18. Groundwater screening evaluation/monitoring plan: 200 Area Treated Effluent Disposal Facility (Project W-049H). Revision 1

    SciTech Connect

    Barnett, D.B.; Davis, J.D.; Collard, L.B.; Freeman, P.B.; Chou, C.J.

    1995-05-01

    This report consists of the groundwater screening evaluation required by Section S.8 of the State Waste Discharge Permit for the 200 Area TEDF. Chapter 1.0 describes the purpose of the groundwater monitoring plan. The information in Chapter 2.0 establishes a water quality baseline for the facility and is the groundwater screening evaluation. The following information is included in Chapter 2.0: Facility description;Well locations, construction, and development data; Geologic and hydrologic description of the site and affected area; Ambient groundwater quality and current use; Water balance information; Hydrologic parameters; Potentiometric map, hydraulic gradients, and flow velocities; Results of infiltration and hydraulic tests; Groundwater and soils chemistry sampling and analysis data; Statistical evaluation of groundwater background data; and Projected effects of facility operation on groundwater flow and water quality. Chapter 3.0 defines, based on the information in Chapter 2.0, how effects of the TEDF on the environment will be evaluated and how compliance with groundwater quality standards will be documented in accordance with the terms and conditions of the permit. Chapter 3.0 contains the following information: Media to be monitored; Wells proposed as the point of compliance in the uppermost aquifer; Basis for monitoring well network and evidence of monitoring adequacy; Contingency planning approach for vadose zone monitoring wells; Which field parameters will be measured and how measurements will be made; Specification of constituents to be sampled and analyzed; and Specification of the sampling and analysis procedures that will be used. Chapter 4.0 provides information on how the monitoring results will be reported and the proposed frequency of monitoring and reporting. Chapter 5.0 lists all the references cited in this monitoring plan. These references should be consulted for additional or more detailed information.

  19. Lessons Learned from the 200 West Pump and Treatment Facility Construction Project at the US DOE Hanford Site - A Leadership for Energy and Environmental Design (LEED) Gold-Certified Facility - 13113

    SciTech Connect

    Dorr, Kent A.; Freeman-Pollard, Jhivaun R.; Ostrom, Michael J.

    2013-07-01

    CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built to an accelerated schedule with American Recovery and Reinvestment Act (ARRA) funds. There were many contractual, technical, configuration management, quality, safety, and Leadership in Energy and Environmental Design (LEED) challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility to meet DOE's mission objective of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012. The project team's successful integration of the project's core values and green energy technology throughout design, procurement, construction, and start-up of this complex, first-of-its-kind Bio Process facility resulted in successful achievement of DOE's mission objective, as well as attainment of LEED GOLD certification (Figure 1), which makes this Bio Process facility the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. (authors)

  20. Evaluation of the effects of underground water usage and spillage in the Exploratory Studies Facility; Yucca Mountain Site Characterization Project

    SciTech Connect

    Dunn, E.; Sobolik, S.R.

    1993-12-01

    The Yucca Mountain Site Characterization Project is studying Yucca Mountain in southwestern Nevada as a potential site for a high-level radioactive waste repository. Analyses reported herein were performed to support the design of site characterization activities so that these activities will have a minimal impact on the ability of the site to isolate waste and a minimal impact on underground tests performed as part of the characterization process. These analyses examine the effect of water to be used in the underground construction and testing activities for the Exploratory Studies Facility on in situ conditions. Underground activities and events where water will be used include construction, expected but unplanned spills, and fire protection. The models used predict that, if the current requirements in the Exploratory Studies Facility Design Requirements are observed, water that is imbibed into the tunnel wall rock in the Topopah Springs welded tuff can be removed over the preclosure time period by routine or corrective ventilation, and also that water imbibed into the Paintbrush Tuff nonwelded tuff will not reach the potential waste storage area.

  1. EERC pilot-scale CFBC evaluation facility Project CFB test results. Topical report, Task 7.30

    SciTech Connect

    Mann, M.D.; Hajicek, D.R.; Henderson, A.K.; Moe, T.A.

    1992-09-01

    Project CFB was initiated at the University of North Dakota Energy and Environmental Research Center (EERC) in May 1988. Specific goals of the project were to (1) construct a circulating fluidized-bed combustor (CFBC) facility representative of the major boiler vendors` designs with the capability of producing scalable data, (2) develop a database for use in making future evaluations of CFBC technology, and (3) provide a facility for evaluating fuels, free of vendor bias for use in the - energy industry. Five coals were test-burned in the 1-MWth unit: North Dakota and Asian lignites, a Wyoming subbituminous, and Colorado and Pennsylvania bituminous coats. A total of 54 steady-state test periods were conducted, with the key test parameters being the average combustor temperature, excess air, superficial gas velocity, calcium-to-sulfur molar ratio, and the primary air-to-secondary air split. The capture for a coal fired in a CFBC is primarily dependent upon the total alkali-to-sulfur ratio. The required alkali-to ratio for 90% sulfur retention ranged from 1.4 to 4.9, depending upon coal type. While an alkali-to-ratio of 4.9 was required to meet 90% sulfur retention for the Salt Creek coal versus 1.4 for the Asian lignite, the total amount of sorbent addition required is much less for the Salt Creek coal, 4.2 pound sorbent per million Btu coal input, versus 62 pound/million Btu for the Asian lignite. The bituminous coals tested show optimal capture at combustor temperatures of approximately 1550{degree}F, with low-rank coals having optimal sulfur capture approximately 100{degree}F lower.

  2. Preclosure radiological safety evaluation: Exploratory Studies Facility; Yucca Mountain Site Characterization Project

    SciTech Connect

    Schelling, F.J.; Smith, J.D.

    1993-07-01

    A radiological safety evaluation is performed to determine the impacts of Exploratory Studies Facility (ESF) design changes on the preclosure public radiological safety for a potential nuclear waste repository at Yucca Mountain, Nevada. Although the ESF design has undergone significant modification, incorporation of the modified design requires only modest changes to the conceptual repository configuration. To the extent feasible, the results of earlier safety evaluations presented in SAND84-2641, SAND88-7061, and SAND89-7024, which were based on the original ESF configuration, are compared with the results for the modified configuration. This comparison provides an estimate of the range of analysis uncertainty. This preliminary analysis indicates that there are no Q-scenarios, which are defined as those scenarios with a net occurrence probability of greater than 10{sup {minus}6}/yr and produce a radiological dose at the 5-km controlled area boundary of greater than 0.5 rem. The analysis yielded estimates for an underground accident of a probability of 3.8 {times} 10{sup {minus}15}/yr and a dose of 1.5 rem. For a surface-initiated accident, a probability of 1.5 {times} 10{sup {minus}12}/yr and a dose of 0.6 rem was estimated.

  3. Deactivation of the P, C, and R Reactor Disassembly Basins at the SRS

    SciTech Connect

    Pickett, J.B.

    2000-12-06

    The Facilities Disposition Division (FDD) at the Savannah River Site is engaged in planning the deactivation/closure of three of the site's five reactor disassembly basins. Activities are currently underway at 105-R Disassembly Basin and will continue with the 105-P and 105-C disassembly basins. The basins still contain the cooling and shielding water that was present when operations ceased. Low concentrations of radionuclides are present, with tritium, Cs-137, and Sr-90 being the major contributors. Although there is no evidence that any of the basins have leaked, the 50-year-old facilities will eventually contaminate the surrounding groundwaters. The FDD is pursuing a pro-active solution to close the basins in-place and prevent a release to the groundwater. In-situ ion-exchange is currently underway at the R-Reactor Disassembly Basin to reduce the Cs and Sr concentrations to levels that would allow release of the treated water to previously used on-site cooling ponds. A NEPA Environmental Assessment (EA) is being prepared to propose the preferred closure alternative for each of the three basins. The EA will be the primary mechanism to inform the public and gain stakeholder and regulatory approval.

  4. Activation-deactivation of self-healing in supramolecular rubbers

    NASA Astrophysics Data System (ADS)

    Corte, Laurent; Maes, Florine; Montarnal, Damien; Cantournet, Sabine; Tournilhac, Francois; Leibler, Ludwik; Mines-Paristech Cnrs (Umr7633) Team; Espci-Paristech Cnrs (Umr7167) Team

    2011-03-01

    Self-healing materials have the ability to restore autonomously their structural integrity after damage. Such a remarkable property was obtained recently in supramolecular rubbers formed by a network of small molecules associated via hydrogen bonds. Here we explore this self-healing through an original tack experiment where two parts of supramolecular rubber are brought into contact and then separated. These experiments reveal that a strong self-healing ability is activated by damage even though the surfaces of a molded part are weakly self-adhesive. In our testing conditions, a five minute contact between crack faces is sufficient to recover most mechanical properties of the bulk while days are required to obtain such adhesion levels with melt-pressed surfaces. We show that the deactivation of this self-healing ability seems unexpectedly slow as compared to the predicted dynamics of supramolecular networks. Fracture faces stored apart at room temperature still self-heal after days but are fully deactivated within hours by annealing. Combining these results with microstructural observations gives us a deeper insight into the mechanisms involved in this self-healing process.

  5. Reoxidation and deactivation of supported cobalt Fischer-Tropsch catalysts

    SciTech Connect

    Schanke, D.; Bergene, E.; Adnanes, E.

    1995-12-31

    As a result of the highly exothermic nature of the Fischer-Tropsch reaction, heat transfer considerations limit the maximum conversion per pass in fixed-bed processes, whereas slurry reactors can operate at higher conversions. During Fischer-Tropsch synthesis on cobalt catalysts, high conversions will generate high partial pressures of water at the reactor exit, due to the low water gas shift activity of cobalt. In addition, the extensive back-mixing in slurry reactors will give a relatively uniform concentration profile in the reactor, characterized by a high concentration of water and low reactant concentrations. From the commercial iron-catalyzed Fischer-Tropsch synthesis in fixed-bed (Arge) reactors it is known that the catalyst deactivates by oxidation of iron by CO{sub 2} and H{sub 2}O near the exit of the reactor. Although bulk oxidation of cobalt during Fischer-Tropsch synthesis is not thermodynamically favored, it was early speculated that surface oxidation of cobalt could occur during Fischer-Tropsch synthesis. The purpose of the present work is to describe the influence of water on the deactivation behavior of Al{sub 2}O{sub 3} supported cobalt catalysts. The possibility of cobalt oxidation during Fischer-Tropsch synthesis was investigated by model studies.

  6. Dopaminergic Modulation of Medial Prefrontal Cortex Deactivation in Parkinson Depression.

    PubMed

    Andersen, Anders H; Smith, Charles D; Slevin, John T; Kryscio, Richard J; Martin, Catherine A; Schmitt, Frederick A; Blonder, Lee X

    2015-01-01

    Parkinson's disease (PD) is associated with emotional abnormalities. Dopaminergic medications ameliorate Parkinsonian motor symptoms, but less is known regarding the impact of dopaminergic agents on affective processing, particularly in depressed PD (dPD) patients. The aim of this study was to examine the effects of dopaminergic pharmacotherapy on brain activation to emotional stimuli in depressed versus nondepressed Parkinson disease (ndPD) patients. Participants included 18 ndPD patients (11 men, 7 women) and 10 dPD patients (7 men, 3 women). Patients viewed photographs of emotional faces during functional MRI. Scans were performed while the patient was taking anti-Parkinson medication and the day after medication had been temporarily discontinued. Results indicate that dopaminergic medications have opposite effects in the prefrontal cortex depending upon depression status. DPD patients show greater deactivation in the ventromedial prefrontal cortex (VMPFC) on dopaminergic medications than off, while ndPD patients show greater deactivation in this region off drugs. The VMPFC is in the default-mode network (DMN). DMN activity is negatively correlated with activity in brain systems used for external visual attention. Thus dopaminergic medications may promote increased attention to external visual stimuli among dPD patients but impede normal suppression of DMN activity during external stimulation among ndPD patients. PMID:26793404

  7. De-Alerting and De-Activating Strategic Nuclear Weapons

    SciTech Connect

    KARAS, THOMAS H.

    2001-04-01

    Despite the end of the Cold War, the US and Russia continue to maintain their ICBMs and many SLBMs in a highly alerted state--they are technically prepared to launch the missiles within minutes of a command decision to do so. Some analysts argue that, particularly in light of the distressed condition of the Russian military, these high alert conditions are tantamount to standing on the edge of a nuclear cliff from which we should now step back. They have proposed various bilateral ''de-alerting'' measures, to be taken prior to and outside the context of the formal strategic arms reduction treaty (START) process. This paper identifies several criteria for a stable de-alerting regime, but fails to find de-alerting measures that convincingly satisfy the criteria. However, some de-alerting measures have promise as de-activation measures for systems due for elimination under the START II and prospective START III treaties. Moreover, once these systems are deactivated, a considerable part of the perceived need to keep nuclear forces on high alert as a survivability hedge will be reduced. At the same time, the U.S. and Russia could consider building on their earlier cooperative actions to reduce the risk of inadvertent nuclear war by enhancing their communications links and possibly joining in efforts to improve early warning systems.

  8. Routes for deactivation of different autothermal reforming catalysts

    NASA Astrophysics Data System (ADS)

    Pasel, Joachim; Wohlrab, Sebastian; Kreft, Stefanie; Rotov, Mikhail; Löhken, Katrin; Peters, Ralf; Stolten, Detlef

    2016-09-01

    Fuel cell systems with integrated autothermal reforming units require active and robust catalysts for H2 production. In pursuit of this, an experimental screening of catalysts utilized in the autothermal reforming of commercial diesel fuels is performed. The catalysts incorporate a monolithic cordierite substrate, an oxide support (γ-Al2O3, La-Al2O3, CeO2, Gd-CeO2, ZrO2, Y-ZrO2) and Rh as the active phase. Experiments are run by widely varying the O2/C and H2O/C molar ratios at different gas hourly space velocities. In most cases, this provokes accelerated catalyst deactivation and permits an informative comparison of the catalysts. Fresh and aged catalysts are characterized by temperature-programmed methods, thermogravimetry and transmission electron microscopy to find correlations with catalytic activity and stability. Using this approach, routes for catalyst deactivation are identified, together with causes of different catalytic activities. Suitable reaction conditions can be derived from our results for the operation of reactors for autothermal reforming at steady-state and under transient reaction conditions, which helps improve the efficiency and the stability of fuel cell systems.

  9. Dopaminergic Modulation of Medial Prefrontal Cortex Deactivation in Parkinson Depression

    PubMed Central

    Andersen, Anders H.; Smith, Charles D.; Slevin, John T.; Kryscio, Richard J.; Martin, Catherine A.; Schmitt, Frederick A.; Blonder, Lee X.

    2015-01-01

    Parkinson's disease (PD) is associated with emotional abnormalities. Dopaminergic medications ameliorate Parkinsonian motor symptoms, but less is known regarding the impact of dopaminergic agents on affective processing, particularly in depressed PD (dPD) patients. The aim of this study was to examine the effects of dopaminergic pharmacotherapy on brain activation to emotional stimuli in depressed versus nondepressed Parkinson disease (ndPD) patients. Participants included 18 ndPD patients (11 men, 7 women) and 10 dPD patients (7 men, 3 women). Patients viewed photographs of emotional faces during functional MRI. Scans were performed while the patient was taking anti-Parkinson medication and the day after medication had been temporarily discontinued. Results indicate that dopaminergic medications have opposite effects in the prefrontal cortex depending upon depression status. DPD patients show greater deactivation in the ventromedial prefrontal cortex (VMPFC) on dopaminergic medications than off, while ndPD patients show greater deactivation in this region off drugs. The VMPFC is in the default-mode network (DMN). DMN activity is negatively correlated with activity in brain systems used for external visual attention. Thus dopaminergic medications may promote increased attention to external visual stimuli among dPD patients but impede normal suppression of DMN activity during external stimulation among ndPD patients. PMID:26793404

  10. Ground-water monitoring compliance projects for Hanford Site facilities: Volume 1, The report and Appendix A, Progress report for the period October 1 to December 31, 1986

    SciTech Connect

    Not Available

    1987-02-01

    This report documents recent progress on ground-water monitoring projects for four Hanford Site facilities: the 300 Area Process Trenches, the 183-H Solar Evaporation Basins, the 200 Area Low-Level Burial Grounds, and the Nonradioactive Dangerous Waste (NRDW) Landfill. The existing ground-water monitoring projects for the first two facilities named in the paragraph above are currently being expanded by adding new wells to the networks. During the reporting period, sampling of the existing wells continued on a monthly basis, and the analytical results for samples collected from September through November 1986 are included and discussed in this document. 8 refs., 41 figs., 7 tabs.

  11. Diagnosis of deactivation sources for vanadium catalysts used in SO 2 oxidation reaction and optimization of vanadium extraction from deactivated catalysts

    NASA Astrophysics Data System (ADS)

    Ksibi, Mohamed; Elaloui, Elimam; Houas, Ammar; Moussa, Noomen

    2003-12-01

    Physico-chemical analysis (X-ray, FTIR) and/or methanol oxidation reaction test were performed on fresh and deactivated vanadium catalysts used in H 2SO 4 manufacturing. It allowed the diagnosis of catalyst deactivation sources, as well as the processes of regenerating and recycling the worn out catalyst in converter. One of these processes is hydrometallurgical method. It consists in treating the deactivated catalyst with alkaline or acidic reagents and forming vanadate solution. A simple and non-costly operation of chemical attack permits the extraction of vanadium from silica in deactivated catalyst. The extracted vanadium can be used for the confection of regenerated catalysts or metallic tools. After optimization, this method can be used for industrial application.

  12. The impact of CFD on development test facilities - A National Research Council projection. [computational fluid dynamics

    NASA Technical Reports Server (NTRS)

    Korkegi, R. H.

    1983-01-01

    The results of a National Research Council study on the effect that advances in computational fluid dynamics (CFD) will have on conventional aeronautical ground testing are reported. Current CFD capabilities include the depiction of linearized inviscid flows and a boundary layer, initial use of Euler coordinates using supercomputers to automatically generate a grid, research and development on Reynolds-averaged Navier-Stokes (N-S) equations, and preliminary research on solutions to the full N-S equations. Improvements in the range of CFD usage is dependent on the development of more powerful supercomputers, exceeding even the projected abilities of the NASA Numerical Aerodynamic Simulator (1 BFLOP/sec). Full representation of the Re-averaged N-S equations will require over one million grid points, a computing level predicted to be available in 15 yr. Present capabilities allow identification of data anomalies, confirmation of data accuracy, and adequateness of model design in wind tunnel trials. Account can be taken of the wall effects and the Re in any flight regime during simulation. CFD can actually be more accurate than instrumented tests, since all points in a flow can be modeled with CFD, while they cannot all be monitored with instrumentation in a wind tunnel.

  13. Attention, Emotion, and Deactivation of Default Activity in Inferior Medial Prefrontal Cortex

    ERIC Educational Resources Information Center

    Geday, Jacob; Gjedde, Albert

    2009-01-01

    Attention deactivates the inferior medial prefrontal cortex (IMPC), but it is uncertain if emotions can attenuate this deactivation. To test the extent to which common emotions interfere with attention, we measured changes of a blood flow index of brain activity in key areas of the IMPC with positron emission tomography (PET) of labeled water…

  14. Geology of the ECRB Cross Drift-Exploratory Studies Facility, Yucca Mountain Project, Yucca Mountain, Nevada

    SciTech Connect

    DOE,

    1999-01-01

    The Enhanced Characterization of the Repository Block Cross Drift (Cross Drift) excavated at Yucca Mountain is being studied to determine its suitability as a permanent high-level nuclear waste repository. This report presents a summary of data collected by the U.S. Bureau of Reclamation (USBR) personnel on behalf of the U.S. Geological Survey (USGS) for the Department of Energy in the Cross Drift from Sta. 00+00 to 26+64. This report includes descriptions of lithostratigraphic units, an analysis of data from full-periphery geologic maps (FPGM) and detailed line survey (DLS) data, a detailed description of the Solitario Canyon Fault zone (SCFZ), and an analysis of geotechnical and engineering characteristics. The Cross Drift is excavated entirely within the Topopah Spring Tuff formation of the Paintbrush Group. Units exposed in the crystal-poor member of the Topopah Spring Tuff, include the Topopah Spring crystal-poor upper lithophysal zone (Tptpul) (Sta. 0+00 to 10+15), the Topopah Spring crystal-poor middle nonlithophysal zone (Tptpmn) (Sta. 10+15 to 14+44), the Topopah Spring crystal-poor lower lithophysal zone (Tptpll) (Sta. 14+44 to 23+26), and the Topopah Spring crystal-poor lower nonlithophysal zone (Tptpln) (Sta. 23+26 to 25+85). The lower portion of the Topopah Spring crystal-rich lithophysal transition subzone (Tptrl1) is exposed on the west side of the Solitario Canyon fault from Sta. 26+57.5 to 26+64. Lithologically, the units exposed in the Cross Drift are similar in comparable stratigraphic intervals of the Exploratory Studies Facility (ESF), particularly in terms of welding, secondary crystallization, fracturing, and type, size, color, and abundance of pumice and lithic clasts. The most notable difference is the lack of the intensely fractured zone (IFZ) in the Cross Drift. The as-built cross section and the pre-construction cross section compare favorably. Lithostratigraphic contacts and structures on the pre-construction cross section were

  15. 300 Area D4 Project 2nd Quarter FY06 Building Completion Report

    SciTech Connect

    David S. Smith

    2006-06-26

    This report documents the deactivation, decontamination, decommissioning, and demolition of 16 buildings in the 300 Area of the Hanford Site. The D4 of these facilities included characterization, engineering, removal of hazardous and radiologically contaminated materials, equipment removal, utility disconnection, deactivation, decontamination, demolition of the structure, and stabilization or removal of the remaining slab and foundation as appropriate.

  16. 300 Area D4 Project 3rd Quarter Fiscal Year 2006 Building Completion Report

    SciTech Connect

    D. S. Smith

    2006-09-25

    This report documents the deactivation, decontamination, decommissioning, and demolition of five buildings in the 300 Area of the Hanford Site. The D4 of these facilities included characterization, engineering, removal of hazardous and radiologically contaminated materials, equipment removal, utility disconnection, deactivation, decontamination, demolition of the structure, and stabilization or removal of the remaining slab and foundation as appropriate.

  17. A critical evaluation of migraine trigger site deactivation surgery.

    PubMed

    Mathew, Paul G

    2014-01-01

    Migraine headache trigger site deactivation surgery is a term that encompasses 4 different surgical procedures that are performed based on headache onset location for the preventative treatment of migraine headaches. Multiple studies have demonstrated some efficacy of these procedures, but closer evaluation of the methodology of these studies reveals major flaws in study design. In this article, the author provides an overview of the procedures and presurgical screening tools, as well as a critical evaluation of 2 of the major studies that have been published. In addition, the author provides his opinion on future study designs that may help to better determine the potential efficacy of these experimental procedures and potential headache subtypes (contact point headache, supraorbital neuralgia, and occipital neuralgia) that may respond to peripheral decompression surgery. PMID:24116941

  18. Lessons Learned from the 200 West Pump and Treatment Facility Construction Project at the US DOE Hanford Site - A Leadership for Energy and Environmental Design (LEED) Gold-Certified Facility

    SciTech Connect

    Dorr, Kent A.; Ostrom, Michael J.; Freeman-Pollard, Jhivaun R.

    2013-01-11

    CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy’s (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built to an accelerated schedule with American Recovery and Reinvestment Act (ARRA) funds. There were many contractual, technical, configuration management, quality, safety, and Leadership in Energy and Environmental Design (LEED) challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility to meet DOE’s mission objective of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012. The project team’s successful integration of the project’s core values and green energy technology throughout design, procurement, construction, and start-up of this complex, first-of-its-kind Bio Process facility resulted in successful achievement of DOE’s mission objective, as well as attainment of LEED GOLD certification, which makes this Bio Process facility the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award.

  19. β-Arrestin-dependent deactivation of mouse melanopsin.

    PubMed

    Cameron, Evan G; Robinson, Phyllis R

    2014-01-01

    In mammals, the expression of the unusual visual pigment, melanopsin, is restricted to a small subset of intrinsically photosensitive retinal ganglion cells (ipRGCs), whose signaling regulate numerous non-visual functions including sleep, circadian photoentrainment and pupillary constriction. IpRGCs exhibit attenuated electrical responses following sequential and prolonged light exposures indicative of an adaptational response. The molecular mechanisms underlying deactivation and adaptation in ipRGCs however, have yet to be fully elucidated. The role of melanopsin phosphorylation and β-arrestin binding in this adaptive process is suggested by the phosphorylation-dependent reduction of melanopsin signaling in vitro and the ubiquitous expression of β-arrestin in the retina. These observations, along with the conspicuous absence of visual arrestin in ipRGCs, suggest that a β-arrestin terminates melanopsin signaling. Here, we describe a light- and phosphorylation- dependent reduction in melanopsin signaling mediated by both β-arrestin 1 and β-arrestin 2. Using an in vitro calcium imaging assay, we demonstrate that increasing the cellular concentration of β-arrestin 1 and β-arrestin 2 significantly increases the rate of deactivation of light-activated melanopsin in HEK293 cells. Furthermore, we show that this response is dependent on melanopsin carboxyl-tail phosphorylation. Crosslinking and co-immunoprecipitation experiments confirm β-arrestin 1 and β-arrestin 2 bind to melanopsin in a light- and phosphorylation- dependent manner. These data are further supported by proximity ligation assays (PLA), which demonstrate a melanopsin/β-arrestin interaction in HEK293 cells and ipRGCs. Together, these results suggest that melanopsin signaling is terminated in a light- and phosphorylation-dependent manner through the binding of a β-arrestin within the retina. PMID:25401926

  20. Deactivation of Escherichia coli by the plasma needle

    NASA Astrophysics Data System (ADS)

    Sladek, R. E. J.; Stoffels, E.

    2005-06-01

    In this paper we present a parameter study on deactivation of Escherichia coli (E. coli) by means of a non-thermal plasma (plasma needle). The plasma needle is a small-sized (1 mm) atmospheric glow sustained by radio-frequency excitation. This plasma will be used to disinfect heat-sensitive objects; one of the intended applications is in vivo deactivation of dental bacteria: destruction of plaque and treatment of caries. We use E. coli films plated on agar dishes as a model system to optimize the conditions for bacterial destruction. Plasma power, treatment time and needle-to-sample distance are varied. Plasma treatment of E. coli films results in formation of a bacteria-free void with a size up to 12 mm. 104-105 colony forming units are already destroyed after 10 s of treatment. Prolongation of treatment time and usage of high powers do not significantly improve the destruction efficiency: short exposure at low plasma power is sufficient. Furthermore, we study the effects of temperature increase on the survival of E. coli and compare it with thermal effects of the plasma. The population of E. coli heated in a warm water bath starts to decrease at temperatures above 40°C. Sample temperature during plasma treatment has been monitored. The temperature can reach up to 60°C at high plasma powers and short needle-to-sample distances. However, thermal effects cannot account for bacterial destruction at low power conditions. For safe and efficient in vivo disinfection, the sample temperature should be kept low. Thus, plasma power and treatment time should not exceed 150 mW and 60 s, respectively.

  1. Resource Conservation and Recovery Act ground-water monitoring projects for Hanford facilities: Progress Report for the Period April 1 to June 30, 1989

    SciTech Connect

    Smith, R.M.; Bates, D.J.; Lundgren, R.E.

    1989-09-01

    This report describes the progress of 13 Hanford ground-water monitoring projects for the period April 1 to June 30, 1989. These projects are for the 300 area process trenches (300 area), 183-H solar evaporation basins (100-H area), 200 areas low-level burial grounds, nonradioactive dangerous waste landfill (southeast of the 200 areas), 1301-N liquid waste disposal facility (100-N area), 1324-N surface impoundment and 1324-NA percolation pond (100-N area), 1325-N liquid waste disposal facility (100-N area), 216-A-10 crib (200-east area), 216-A-29 ditch (200-east area), 216-A-36B crib (200-east area), 216-B-36B crib (200-east area), 216-B-3 pond (east of the 200-east area), 2101-M pond (200-east area), grout treatment facility (200-east area).

  2. The PixFEL project: development of advanced X-ray pixel detectors for application at future FEL facilities

    NASA Astrophysics Data System (ADS)

    Rizzo, G.; Comotti, D.; Fabris, L.; Grassi, M.; Lodola, L.; Malcovati, P.; Manghisoni, M.; Ratti, L.; Re, V.; Traversi, G.; Vacchi, C.; Batignani, G.; Bettarini, S.; Casarosa, G.; Forti, F.; Morsani, F.; Paladino, A.; Paoloni, E.; Dalla Betta, G.-F.; Pancheri, L.; Verzellesi, G.; Xu, H.; Mendicino, R.; Benkechkache, M. A.

    2015-02-01

    The PixFEL project aims to develop an advanced X-ray camera for imaging suited for the demanding requirements of next generation free electron laser (FEL) facilities. New technologies can be deployed to boost the performance of imaging detectors as well as future pixel devices for tracking. In the first phase of the PixFEL project, approved by the INFN, the focus will be on the development of the microelectronic building blocks, carried out with a 65 nm CMOS technology, implementing a low noise analog front-end channel with high dynamic range and compression features, a low power ADC and high density memory. At the same time PixFEL will investigate and implement some of the enabling technologies to assembly a seamless large area X-ray camera composed by a matrix of multilayer four-side buttable tiles. A pixel matrix with active edge will be developed to minimize the dead area of the sensor layer. Vertical interconnection of two CMOS tiers will be explored to build a four-side buttable readout chip with small pixel pitch and all the on-board required functionalities. The ambitious target requirements of the new pixel device are: single photon resolution, 1 to 104 photons @ 1 keV to 10 keV input dynamic range, 10-bit analog to digital conversion up to 5 MHz, 1 kevent in-pixel memory and 100 μm pixel pitch. The long term goal of PixFEL will be the development of a versatile X-ray camera to be operated either in burst mode (European XFEL), or in continuous mode to cope with the high frame rates foreseen for the upgrade phase of the LCLS-II at SLAC.

  3. The User Community and a Multi-Mission Data Project: Services, Experiences and Directions of the Space Physics Data Facility

    NASA Technical Reports Server (NTRS)

    Fung, Shing F.; Bilitza, D.; Candey, R.; Chimiak, R.; Cooper, John; Fung, Shing; Harris, B.; Johnson R.; King, J.; Kovalick, T.; Leckner, H.; Papitashvili, N.; Roberts, Aaron

    2008-01-01

    From a user's perspective, the multi-mission data and orbit services of NASA's Space Physics Data Facility (SPDF) project offer a unique range of important data and services highly complementary to other services presently available or now evolving in the international heliophysics data environment. The VSP (Virtual Space Physics Observatory) service is an active portal to a wide range of distributed data sources. CDAWeb (Coordinate Data Analysis Web) enables plots, listings and file downloads for current data cross the boundaries of missions and instrument types (and now including data from THEMIS and STEREO). SSCWeb, Helioweb and our 3D Animated Orbit Viewer (TIPSOD) provide position data and query logic for most missions currently important to heliophysics science. OMNIWeb with its new extension to 1- and 5-minute resolution provides interplanetary parameters at the Earth's bow shock as a unique value-added data product. SPDF also maintains NASA's CDF (common Data Format) standard and a range of associated tools including translation services. These capabilities are all now available through webservices-based APIs as well as through our direct user interfaces. In this paper, we will demonstrate the latest data and capabilities now supported in these multi-mission services, review the lessons we continue to learn in what science users need and value in this class of services, and discuss out current thinking to the future role and appropriate focus of the SPDF effort in the evolving and increasingly distributed heliophysics data environment.

  4. Mixed and Low-Level Treatment Facility Project. Appendix B, Waste stream engineering files, Part 1, Mixed waste streams

    SciTech Connect

    Not Available

    1992-04-01

    This appendix contains the mixed and low-level waste engineering design files (EDFS) documenting each low-level and mixed waste stream investigated during preengineering studies for Mixed and Low-Level Waste Treatment Facility Project. The EDFs provide background information on mixed and low-level waste generated at the Idaho National Engineering Laboratory. They identify, characterize, and provide treatment strategies for the waste streams. Mixed waste is waste containing both radioactive and hazardous components as defined by the Atomic Energy Act and the Resource Conservation and Recovery Act, respectively. Low-level waste is waste that contains radioactivity and is not classified as high-level waste, transuranic waste, spent nuclear fuel, or 11e(2) byproduct material as defined by DOE 5820.2A. Test specimens of fissionable material irradiated for research and development only, and not for the production of power or plutonium, may be classified as low-level waste, provided the concentration of transuranic is less than 100 nCi/g. This appendix is a tool that clarifies presentation format for the EDFS. The EDFs contain waste stream characterization data and potential treatment strategies that will facilitate system tradeoff studies and conceptual design development. A total of 43 mixed waste and 55 low-level waste EDFs are provided.

  5. Future high intensity ISOL facilities: Selected current R&D topics and possible synergies with other projects

    NASA Astrophysics Data System (ADS)

    Mueller, Alex C.

    2003-05-01

    The long-term future of ISOL facilities will be governed by the quest for ever increasing secondary beam intensities. One important aspect concerns a new generation of high-power driver accelerators which aim at multi-megawatt beam powers, used in a two-step production scheme for fission products. Within the EURISOL study, e.g. a 1 GeV, 5 mA proton has been investigated in some detail. It would be upgradeable in energy and also have, up to a certain extend, the capability for heavy-ion acceleration. The required R&D programme was assessed, and found to be in the mainstream of today's accelerator development which addresses also other projects like accelerator-driven transmutation of nuclear waste, neutrino beams, …. The concomitant development of high-power spallation targets and the secondary uranium targets is the second issue where a lot of R&D effort is done by several communities. Linked to this are also the studies in which photo-fission is used as a "low-cost" option for a dedicated region of the nuclear chart. The present paper will introduce in this general context, and discuss (selected) relevant new experimental results which are obtained in linac in particular.

  6. Deactivation behaviors of zeolite and silica-alumina catalysts in the degradation of polyethylene

    SciTech Connect

    Uemichi, Yoshio; Hattori, Masahiko; Itoh, Toshihiro; Nakamura, Junko; Sugioka, Masatoshi

    1998-03-01

    For chemical recycling of waste plastics, HZSM-5, HY, and H-mordenite zeolites and silica-alumina were examined as catalysts for the degradation of polyethylene in a fixed-bed flow reactor system, and their activities and deactivation behaviors caused by coke deposition were studied. HZSM-5 catalyst was fond to be very effective for the production of gasoline-range fuel oils mainly consisting of isoparaffins and aromatics and showed no deactivation due to a very low yield of coke deposited on the catalyst surface, whereas in the degradation of polystyrene a marked deactivation was observed. Silica-alumina gradually deactivated as time on stream increased, but the degree of deactivation was less than expected from the deposition of a significant amount of coke, probably because the coke deposition in the large pores of the catalyst caused no marked influence on the diffusion of the decomposed fragments involved in the reaction. On the other hand, deactivations of HY and H-mordenite were striking; the latter was most abruptly deactivated, resulting in a marked decrease in the liquid yield. From the surface area measurements of the used catalysts, it was suggested that the pores of HY were sufficiently filled out with coke, while pore blocking by coke occurred in the unidimensional channels of H-mordenite.

  7. Lessons Learned From The 200 West Pump And Treatment Facility Construction Project At The US DOE Hanford Site - A Leadership For Energy And Environmental Design (LEED) Gold-Certified Facility

    SciTech Connect

    Dorr, Kent A.; Ostrom, Michael J.; Freeman-Pollard, Jhivaun R.

    2012-11-14

    CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built in an accelerated manner with American Recovery and Reinvestment Act (ARRA) funds and has attained Leadership in Energy and Environmental Design (LEED) GOLD certification, which makes it the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. There were many contractual, technical, configuration management, quality, safety, and LEED challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility. This paper will present the Project and LEED accomplishments, as well as Lessons Learned by CHPRC when additional ARRA funds were used to accelerate design, procurement, construction, and commissioning of the 200 West Groundwater Pump and Treatment (2W P&T) Facility to meet DOE's mission of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012.

  8. Functions and requirements document, WESF decoupling project, low-level liquid waste system

    SciTech Connect

    Rasmussen, J.H., Fluor Daniel Hanford

    1997-02-27

    The Waste Encapsulation and Storage Facility (WESF) was constructed in 1974 to encapsulate and store cesium and strontium which were isolated at B Plant from underground storage tank waste. The WESF, Building 225-B, is attached physically to the west end of B Plant, Building 221-B, 200 East area. The WESF currently utilizes B Plant facilities for disposing liquid and solid waste streams. With the deactivation of B Plant, the WESF Decoupling Project will provide replacement systems allowing WESF to continue operations independently from B Plant. Four major systems have been identified to be replaced by the WESF Decoupling Project, including the following: Low Level Liquid Waste System, Solid Waste Handling System, Liquid Effluent Control System, and Deionized Water System.

  9. Mechanochemical approach for selective deactivation of external surface acidity of ZSM-5 zeolite catalyst.

    PubMed

    Inagaki, Satoshi; Sato, Koki; Hayashi, Shunsuke; Tatami, Junichi; Kubota, Yoshihiro; Wakihara, Toru

    2015-03-01

    The acid sites associated with the external surface of zeolite particles are responsible for undesirable consecutive reactions, such as isomerization, alkylation, and oligomerization, resulting in a lower selectivity to a target product; therefore, the selective modification (deactivation) of the external surface of zeolite particles has been an important issue in zeolite science. Here, a new method for surface deactivation of zeolite catalyst was tested via a mechanochemical approach using powder composer. Postsynthetic mechanochemical treatment of ZSM-5 zeolite causes a selective deactivation of catalytically active sites existing only on the external surface, as a potentially useful catalyst for highly selective production of p-xylene. PMID:25654542

  10. Transition of Facilities at Hanford to a Stable and Low Cost State

    SciTech Connect

    BAILEY, R.W.

    2000-02-01

    This paper will discuss the implications of focusing on end states and interim end points in the deactivation planning process and managing the budget and personnel to achieve these end points as a ''project,'' not another phase of operations.

  11. Silica supported palladium nanoparticles for the decarboxylation of high-acid feedstocks: Design, deactivation and regeneration

    NASA Astrophysics Data System (ADS)

    Ping, Eric Wayne

    2011-12-01

    The major goals of this thesis were to (1) design and synthesize a supported catalyst with well-defined monodisperse palladium nanoparticles evenly distributed throughout an inorganic oxide substrate with tunable porosity characteristics, (2) demonstrate the catalytic activity of this material in the decarboxylation of long chain fatty acids and their derivatives to make diesel-length hydrocarbons, (3) elucidate the deactivation mechanism of supported palladium catalysts under decarboxylation conditions via post mortem catalyst characterization and develop a regeneration methodology thereupon, and (4) apply this catalytic system to a real low-value biofeedstock. Initial catalyst designs were based on the SBA-15 silica support, but in an effort to maximize loading and minimize mass transfer limitations, silica MCF was synthesized as catalyst support. Functionalization with various silane ligands yielded a surface that facilitated even distribution of palladium precursor salts throughout the catalyst particle, and, after reduction, monodisperse palladium nanoparticles approximately 2 nm in diameter. Complete characterization was performed on this Pd-MCF catalyst. The Pd-MCF catalyst showed high one-time activity in the decarboxylation of fatty acids to hydrocarbons in dodecane at 300°C. Hydrogen was found to be an unnecessary reactant in the absence of unsaturations, but was required in their presence---full hydrogenation of the double bonds occurs before any decarboxylation can take place. The Pd-MCF also exhibited good activity for alkyl esters and glycerol, providing a nice hypothetical description of a stepwise reaction pathway for catalytic decarboxylation of acids and their derivatives. As expected, the Pd-MCF catalyst experienced severe deactivation after only one use. Substantial effort was put into elucidating the nature of this deactivation via post mortem catalyst characterization. H2 chemisorption confirmed a loss of active surface area, but TEM and

  12. Risk-based Prioritization of Facility Decommissioning and Environmental Restoration Projects in the National Nuclear Legacy Liabilities Program at the Chalk River Laboratory - 13564

    SciTech Connect

    Nelson, Jerel G.; Kruzic, Michael; Castillo, Carlos; Pavey, Todd; Alexan, Tamer; Bainbridge, Ian

    2013-07-01

    Chalk River Laboratory (CRL), located in Ontario Canada, has a large number of remediation projects currently in the Nuclear Legacy Liabilities Program (NLLP), including hundreds of facility decommissioning projects and over one hundred environmental remediation projects, all to be executed over the next 70 years. Atomic Energy of Canada Limited (AECL) utilized WorleyParsons to prioritize the NLLP projects at the CRL through a risk-based prioritization and ranking process, using the WorleyParsons Sequencing Unit Prioritization and Estimating Risk Model (SUPERmodel). The prioritization project made use of the SUPERmodel which has been previously used for other large-scale site prioritization and sequencing of facilities at nuclear laboratories in the United States. The process included development and vetting of risk parameter matrices as well as confirmation/validation of project risks. Detailed sensitivity studies were also conducted to understand the impacts that risk parameter weighting and scoring had on prioritization. The repeatable prioritization process yielded an objective, risk-based and technically defendable process for prioritization that gained concurrence from all stakeholders, including Natural Resources Canada (NRCan) who is responsible for the oversight of the NLLP. (authors)

  13. Decommissioning of the 247-F Fuel Manufacturing Facility at the Savannah River Site (SRS)

    SciTech Connect

    Santos, Joseph K.; Chostner, Stephen M.

    2008-01-15

    Building 247-F at SRS was a roughly 110,000 ft{sup 2} two-story facility designed and constructed during the height of the cold war naval buildup to provide additional naval nuclear fuel manufacturing capacity in early 1980's. The manufacturing process employed a wide variety of acids, bases, and other hazardous materials. As the need for naval fuel declined, the facility was shut down and underwent initial deactivation, which was completed in 1990. All process systems were flushed with water and drained using the existing process drain valves. However, since these drains were not always installed at the lowest point in piping and equipment systems, a significant volume of liquid remained after initial deactivation. After initial deactivation, a non-destructive assay of the process area identified approximately 17 ({+-}100%) kg of uranium held up in equipment and piping. The facility was placed in Surveillance and Maintenance mode until 2003, when the decision was made to perform final deactivation, and then decommission the facility. The following lessons were learned as a result of the D and D of building 247-F. Successful D and D of a major radiochemical process building requires significant up-front planning by a team of knowledgeable personnel led by a strong project manager. The level of uncertainty and resultant risk to timely, cost effective project execution was found to be high. Examples of the types of problems encountered which had high potential to adversely impact cost and schedule performance are described below. Low level and sanitary waste acceptance criteria do not allow free liquids in waste containers. These liquids, which are often corrosive, must be safely removed from the equipment before it is loaded to waste containers. Drained liquids must be properly managed, often as hazardous or mixed waste. Tapping and draining of process lines is a dangerous operation, which must be performed carefully. The temptation to become complacent when

  14. Interim Control Strategy for the Test Area North/Technical Support Facility Sewage Treatment Facility Disposal Pond - Two-year Update

    SciTech Connect

    L. V. Street

    2007-04-01

    The Idaho Cleanup Project has prepared this interim control strategy for the U.S. Department of Energy Idaho Operations Office pursuant to DOE Order 5400.5, Chapter 11.3e (1) to support continued discharges to the Test Area North/Technical Support Facility Sewage Treatment Facility Disposal Pond. In compliance with DOE Order 5400.5, a 2-year review of the Interim Control Strategy document has been completed. This submittal documents the required review of the April 2005 Interim Control Strategy. The Idaho Cleanup Project's recommendation is unchanged from the original recommendation. The Interim Control Strategy evaluates three alternatives: (1) re-route the discharge outlet to an uncontaminated area of the TSF-07; (2) construct a new discharge pond; or (3) no action based on justification for continued use. Evaluation of Alternatives 1 and 2 are based on the estimated cost and implementation timeframe weighed against either alternative's minimal increase in protection of workers, the public, and the environment. Evaluation of Alternative 3, continued use of the TSF-07 Disposal Pond under current effluent controls, is based on an analysis of four points: - Record of Decision controls will protect workers and the public - Risk of increased contamination is low - Discharge water will be eliminated in the foreseeable future - Risk of contamination spread is acceptable. The Idaho Cleanup Project recommends Alternative 3, no action other than continued implementation of existing controls and continued deactivation, decontamination, and dismantlement efforts at the Test Area North/Technical Support Facility.

  15. Hazardous Materials Verification and Limited Characterization Report on Sodium and Caustic Residuals in Materials and Fuel Complex Facilities MFC-799/799A

    SciTech Connect

    Gary Mecham

    2010-08-01

    This report is a companion to the Facilities Condition and Hazard Assessment for Materials and Fuel Complex Sodium Processing Facilities MFC-799/799A and Nuclear Calibration Laboratory MFC-770C (referred to as the Facilities Condition and Hazards Assessment). This report specifically responds to the requirement of Section 9.2, Item 6, of the Facilities Condition and Hazards Assessment to provide an updated assessment and verification of the residual hazardous materials remaining in the Sodium Processing Facilities processing system. The hazardous materials of concern are sodium and sodium hydroxide (caustic). The information supplied in this report supports the end-point objectives identified in the Transition Plan for Multiple Facilities at the Materials and Fuels Complex, Advanced Test Reactor, Central Facilities Area, and Power Burst Facility, as well as the deactivation and decommissioning critical decision milestone 1, as specified in U.S. Department of Energy Guide 413.3-8, “Environmental Management Cleanup Projects.” Using a tailored approach and based on information obtained through a combination of process knowledge, emergency management hazardous assessment documentation, and visual inspection, this report provides sufficient detail regarding the quantity of hazardous materials for the purposes of facility transfer; it also provides that further characterization/verification of these materials is unnecessary.

  16. Human Enhancers Are Fragile and Prone to Deactivating Mutations

    PubMed Central

    Li, Shan; Ovcharenko, Ivan

    2015-01-01

    To explore the underlying mechanisms whereby noncoding variants affect transcriptional regulation, we identified nucleotides capable of disrupting binding of transcription factors and deactivating enhancers if mutated (dubbed candidate killer mutations or KMs) in HepG2 enhancers. On average, approximately 11% of enhancer positions are prone to KMs. A comparable number of enhancer positions are capable of creating de novo binding sites via a single-nucleotide mutation (dubbed candidate restoration mutations or RSs). Both KM and RS positions are evolutionarily conserved and tend to form clusters within an enhancer. We observed that KMs have the most deleterious effect on enhancer activity. In contrast, RSs have a smaller effect in increasing enhancer activity. Additionally, the KMs are strongly associated with liver-related Genome Wide Association Study traits compared with other HepG2 enhancer regions. By applying our framework to lymphoblastoid cell lines, we found that KMs underlie differential binding of transcription factors and differential local chromatin accessibility. The gene expression quantitative trait loci associated with the tissue-specific genes are strongly enriched in KM positions. In summary, we conclude that the KMs have the greatest impact on the level of gene expression and are likely to be the causal variants of tissue-specific gene expression and disease predisposition. PMID:25976354

  17. Helium POT System for Maintaining Sample Temperature after Cryocooler Deactivation

    NASA Astrophysics Data System (ADS)

    Haid, B. J.

    2006-04-01

    A system for maintaining a sample at a constant temperature below 10 K after deactivating the cooling source is demonstrated. In this system, the cooling source is a 4 K GM cryocooler that is joined with the sample through an extension that consists of a helium pot and a thermal resistance. Upon stopping the cryocooler, the power applied to a heater located on the sample side of the thermal resistance is decreased gradually to maintain an appropriate temperature rise across the thermal resistance as the helium pot warms. The sample temperature is held constant in this manner without the use of solid or liquid cryogens and without mechanically disconnecting the sample from the cooler. Shutting off the cryocooler significantly reduces sample motion that results from vibration and expansion/contraction of the cold-head housing. The reduction in motion permits certain procedures that are very sensitive to sample position stability, but are performed with limited duration. A proof-of-concept system was built and operated with the helium pot pressurized to the cryocooler's charge pressure. A sample with 200 mW of continuous heat dissipation was maintained at 7 K while the cryocooler operated intermittently with a duty cycle of 9.5 minutes off and 20 minutes on.

  18. The effect of feedstock additives on FCC catalyst deactivation

    SciTech Connect

    Hughes, R.; Koon, C.L.; McGhee, B.

    1995-12-31

    Fluid catalytic cracking is a major petroleum refining process and because of this the deactivation of FCC catalysts by coke deposition has been the subject of considerable investigation during the past 50 years. Nevertheless, a lack of understanding of the fundamental understanding of processes leading to coke formation still exists. Basic studies using Zeolites have usually involved excessively high levels of coke deposits compared to normal FCC operation. The present study addresses coke formation at realistic levels of 0.5 to 1.0% w/w using a standard MAT reactor in which concentrations of 1% and 10% of various additives were added to the n-hexadecane feedstock. These additives included, quinoline, phenanthrene, benzofuran, thianaphthene and indene. The coke formed was characterised by mass spectrometry and was significantly aliphatic in nature, the amount formed increasing in the order quinoline, phenanthrene, thianaphthene, benzofuran, indene. Quinoline acts primarily as a poison, whereas the other additives tend to promote coke formation in n-hexadecane cracking.

  19. Pd migration. 1: A possible reason for the deactivation of pyrolysis gasoline partial hydrogenation catalysts

    SciTech Connect

    Lin, T.B.; Chou, T.C. . Dept. of Chemical Engineering)

    1995-01-01

    The catalyst deactivation of the selective hydrogenation of pyrolysis gasoline of a commercial plant was investigated. Both the fresh and the regenerated catalysts, sampled from the commercial plant, were characterized by the palladium wt %, BET surface area, pore volume, the dispersion of Pd/Al[sub 2]O[sub 3], XRD (X-ray diffraction), and EPMA (electron probe microanalyzer). The results indicated that the major factors affecting the catalyst deactivation of the selective hydrogenation of pyrolysis gasoline of a commercial plant are palladium migration and coke deposition, 53.2%, poor palladium dispersion, 37%, and palladium metal loss, 9.8%. However, the pore mouth plugging, loss of surface area, and phase change of support were the minor factors for catalytic deactivation. The first findings of the effect of palladium migration on the catalyst deactivation of the eggshell palladium profile catalyst are meaningful and important for improving the performance of the catalyst with nonuniform active site distribution.

  20. Deactivation and decommissioning environmental strategy for the Plutonium Finishing Plant (PFP) Complex Hanford Nuclear Reservation

    SciTech Connect

    HOPKINS, A.M.

    2003-02-01

    The overall goal of this strategy is to comply with all applicable environmental laws and regulations and/or compliance agreements during Plutonium Finishing Plant (PFP) stabilization, deactivation, and eventual dismantlement.

  1. Charge separation technique for metal-oxide-silicon capacitors in the presence of hydrogen deactivated dopants

    SciTech Connect

    Witczak, Steven C.; Winokur, Peter S.; Lacoe, Ronald C.; Mayer, Donald C.

    2000-06-01

    An improved charge separation technique for metal-oxide-silicon (MOS) capacitors is presented which accounts for the deactivation of substrate dopants by hydrogen at elevated irradiation temperatures or small irradiation biases. Using high-frequency capacitance-voltage measurements, radiation-induced inversion voltage shifts are separated into components due to oxide trapped charge, interface traps, and deactivated dopants, where the latter is computed from a reduction in Si capacitance. In the limit of no radiation-induced dopant deactivation, this approach reduces to the standard midgap charge separation technique used widely for the analysis of room-temperature irradiations. The technique is demonstrated on a p-type MOS capacitor irradiated with {sup 60}Co {gamma} rays at 100 degree sign C and zero bias, where the dopant deactivation is significant.(c) 2000 American Institute of Physics.

  2. The Commuting Student; A Study of Facilities at Wayne State University. The Final Report of the Commuter Centers Project.

    ERIC Educational Resources Information Center

    Ward, Richard F.; Kurz, Theodore E.

    The urban university campus is studied through a comprehensive view of student patterns. Following an analysis of the life patterns of the commuting student with regard to schedule, environment, and adequacy of educational facilities, recommendations are presented for a number of campus facilities to house activities considered beneficial to the…

  3. Systems Check: Community Colleges Turn to Facilities Assessments to Plan Capital Projects and Avoid Expensive Emergency Repairs

    ERIC Educational Resources Information Center

    Joch, Alan

    2014-01-01

    With an emphasis on planning and cutting costs to make better use of resources, facilities managers at community colleges across the nation have undertaken facilities audits usually with the help of outside engineers. Such assessments analyze the history and structural integrity of buildings and core components on campus, including heating…

  4. Project management plan for Waste Area Grouping 5 Old Hydrofracture Facility tanks contents removal at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1998-06-01

    On January 1, 1992, the US Department of Energy (DOE), the US Environmental Protection Agency (EPA) Region IV, and the Tennessee Department of Environment and Conservation (TDEC) signed a Federal Facility Agreement (FFA) concerning the Oak Ridge Reservation. The FFA requires that inactive liquid low-level (radioactive) waste (LLLW) tanks at Oak Ridge National Laboratory (ORNL) be remediated in accordance with requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). This revision is to update the schedule and designation of responsibilities for the Old Hydrofracture Facility (OHF) tanks contents removal project. The scope of this project is to transfer inventory from the five inactive LLLW tanks at the OHF into the active LLLW system.

  5. Patient perceptions of implantable cardioverter-defibrillator deactivation discussions: A qualitative study

    PubMed Central

    MacIver, Jane; Tibbles, Alana; Billia, Filio; Ross, Heather

    2016-01-01

    Background: There is a class I recommendation for implantable cardioverter-defibrillator deactivation discussions to occur between physicians and heart failure patients. Few studies have reported the patient’s perspective on the timing of implantable cardioverter-defibrillator deactivation discussions. Aim: To determine patient awareness, preferences and timing of implantable cardioverter-defibrillator deactivation discussions. Design: Grounded theory was used to collect and analyze interview data from 25 heart failure patients with an implantable cardioverter-defibrillator. Setting and participants: Patients with an implantable cardioverter-defibrillator, from the Heart Function Clinic at University Health Network (Toronto, Canada). Results: The sample (n = 25) was predominately male (76%) with an average age of 62 years. Patients identified three stages where they felt implantable cardioverter-defibrillator deactivation should be discussed: (1) prior to implantation, (2) with any significant deterioration but while they were of sound mind to engage in and communicate their preferences and (3) at end of life, where patients wished further review of their previously established preferences and decisions about implantable cardioverter-defibrillator deactivation. Most patients (n = 17, 68%) said they would consider deactivation, six (24%) were undecided and two (8%) were adamant they would never turn it off. Conclusion: The patient preferences identified in this study support the need to include information on implantable cardioverter-defibrillator deactivation at implant, with change in clinical status and within broader discussions about end-of-life treatment preferences. Using this process to help patients determine and communicate their implantable cardioverter-defibrillator deactivation preferences may reduce the number of patients experiencing distressing implantable cardioverter-defibrillator shocks at end of life. PMID:27110361

  6. Dopamine Transporters in Striatum Correlated with Deactivation in the Default Mode Network during Visuospatial Attention

    SciTech Connect

    Tomasi, D.; Fowler, J.; Tomasi, D.; Volkow, N.D.; Wang, R.L.; Telang, F.; Wang, Chang, L.; Ernst, T.; /Fowler, J.S.

    2009-06-01

    Dopamine and dopamine transporters (DAT, which regulate extracellular dopamine in the brain) are implicated in the modulation of attention but their specific roles are not well understood. Here we hypothesized that dopamine modulates attention by facilitation of brain deactivation in the default mode network (DMN). Thus, higher striatal DAT levels, which would result in an enhanced clearance of dopamine and hence weaker dopamine signals, would be associated to lower deactivation in the DMN during an attention task. For this purpose we assessed the relationship between DAT in striatum (measured with positron emission tomography and [{sup 11}C]cocaine used as DAT radiotracer) and brain activation and deactivation during a parametric visual attention task (measured with blood oxygenation level dependent functional magnetic resonance imaging) in healthy controls. We show that DAT availability in caudate and putamen had a negative correlation with deactivation in ventral parietal regions of the DMN (precuneus, BA 7) and a positive correlation with deactivation in a small region in the ventral anterior cingulate gyrus (BA 24/32). With increasing attentional load, DAT in caudate showed a negative correlation with load-related deactivation increases in precuneus. These findings provide evidence that dopamine transporters modulate neural activity in the DMN and anterior cingulate gyrus during visuospatial attention. Our findings suggest that dopamine modulates attention in part by regulating neuronal activity in posterior parietal cortex including precuneus (region involved in alertness) and cingulate gyrus (region deactivated in proportion to emotional interference). These findings suggest that the beneficial effects of stimulant medications (increase dopamine by blocking DAT) in inattention reflect in part their ability to facilitate the deactivation of the DMN.

  7. Mixed and Low-Level Waste Treatment Facility Project. Appendix B, Waste stream engineering files: Part 2, Low-level waste streams

    SciTech Connect

    Not Available

    1992-04-01

    Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report documents those studies so the project can continue with an evaluation of programmatic options, system tradeoff studies, and the conceptual design phase of the project. This report, appendix B, comprises the engineering design files for this project study. The engineering design files document each waste steam, its characteristics, and identified treatment strategies.

  8. Mirror Fusion Test Facility-B (MFTF-B) axicell configuration: NbTi magnet system. Manufacturing/producibility final report. Volume 2

    SciTech Connect

    Ritschel, A.J.; White, W.L.

    1985-05-01

    This Final MFTF-B Manufacturing/Producibility Report covers facilities, tooling plan, manufacturing sequence, schedule and performance, producibility, and lessons learned for the solenoid, axicell, and transition coils, as well as a deactivation plan, conclusions, references, and appendices.

  9. Conversion of Biomass-Derived Small Oxygenates over HZSM-5 and its Deactivation Mechanism

    SciTech Connect

    Ramasamy, Karthikeyan K.; Gerber, Mark A.; Flake, Matthew D.; Zhang, He; Wang, Yong

    2014-02-28

    HZSM-5 catalyst deactivation was studied using aqueous feed mixtures containing ethanol, ethanol+ acetic acid, ethanol+ethyl acetate, or ethanol+acetaldehyde in a fixed bed reactor at 360°C and 300psig. Compared to ethanol alone experiment, addition of other oxygenates reduced catalyst life in the order of: ethyl acetatedeactivate the catalyst through a pore-blocking mechanism. Acetic acid deactivates the catalyst through an active site poisoning mechanism or strong adsorption of acetate intermediates on the active sites (hydroxyl groups). Ethanol deactivates the catalyst primarily through its pore-blocking mechanism, but the rate of ethanol deactivation is orders of magnitude slower than that of acetaldehyde. Ethyl acetate hydrolyzes to form acetic acid and ethanol which deactivate the catalyst through its respective mechanisms. In addition, each functional group of oxygenates requires different active sites/catalysts and different operating conditions due to competitive adsorptions on active sites for their conversion to the desired products. Therefore, it is necessary to pre-treat the mixture of oxygenates to produce a feed stream containing the same or similar functional group compounds before converting the feed stream to hydrocarbon compounds over HZSM-5 catalyst.

  10. Facilities for US Radioastronomy.

    ERIC Educational Resources Information Center

    Thaddeus, Patrick

    1982-01-01

    Discusses major developments in radioastronomy since 1945. Topics include proposed facilities, very-long-baseline interferometric array, millimeter-wave telescope, submillimeter-wave telescope, and funding for radioastronomy facilities and projects. (JN)

  11. Ground-water monitoring compliance projects for Hanford Site facilities: Progress report for the period January 1--March 31, 1988: Volume 1, Text

    SciTech Connect

    Not Available

    1988-05-01

    This report describes the progress of eight Hanford Site ground-water monitoring projects for the period January 1 to March 31, 1988. The facilities represented by the eight projects are the 300 Area Process trenches, 183-H Solar Evaporation Basins, 200 Areas Low-Level Burial Grounds, Nonradioactive Dangerous Waste Landfill, 216-A-36B Crib, 1301-N Liquid Waste Disposal Facility, 1325-N Liquid Waste Disposal Facility, and 1324-N/NA Surface Impoundment and Percolation Ponds. The latter four projects are included in this series of quarterly reports for the first time. This report is the seventh in a series of periodic status reports; the first six cover the period from May 1, 1986, through December 31, 1987 (PNL 1986; 1987a, b, c, d; 1988a). This report satisfies the requirements of Section 17B(3) of the Consent Agreement and Compliance Order issued by the Washington State Department of Ecology (1986a) to the US Department of Energy-Richland Operations Office. 13 refs., 19 figs., 24 tabs.

  12. 300 Area D4 Project Fiscal Year 2009 Building Completion Report

    SciTech Connect

    B. J. Skwarek

    2010-01-27

    This report summarizes the deactivation, decontamination, decommissioning, and demolition activities of seven facilities in the 300 Area of the Hanford Site in fiscal year 2009. The D4 of these facilities included characterization; engineering; removal of hazardous and radiologically contaminated materials; equipment removal; utility disconnection; deactivation, decontamination, demolition of the structure; and stabilization or removal of slabs and foundations. This report also summarizes the nine below-grade slabs/foundations removed in FY09 of buildings demolished in previous fiscal years.

  13. Project People 2: An extended interview study of behavior response patterns in health care facility fire incidents

    NASA Astrophysics Data System (ADS)

    Bryan, J. L.

    The data collected in a taped interview study involving a population of 150 facility staff personnel, 53 fire department personnel and 9 patients are presented and discussed. A physical examination and analysis of the fire incident area of the facility was conducted by experienced fire protection engineers to determine the physical area of fire origin with the flame and smoke propagation patterns. Fire department personnel were interviewed to obtain observations of flame and smoke propagation. Facility personnel and patients were interviewed to determine the human behavior responses of the participants during the fire incident and to determine their perception of the fire incident threat.

  14. Task deactivation reductions and atrophy within parietal default mode regions are overlapping but only weakly correlated in mild cognitive impairment

    PubMed Central

    Threlkeld, Zachary D.; Jicha, Greg A.; Smith, Charles D.; Gold, Brian T.

    2012-01-01

    Reduced task deactivation within regions of the default mode network (DMN) has been frequently reported in Alzheimer’s disease (AD) and amnestic mild cognitive impairment (aMCI). As task deactivations reductions become increasingly used in the study of early AD states, it is important to understand their relationship to atrophy. To address this issue, the present study compared task deactivation reductions during a lexical decision task and atrophy in aMCI, using a series of parallel voxel-wise and region-wise analyses of fMRI and structural data. Our results identified multiple regions within parietal cortex as convergence areas of task deactivation and atrophy in aMCI. Relationships between parietal regions showing overlapping task deactivation reductions and atrophy in aMCI were then explored. Regression analyses demonstrated minimal correlation between task deactivation reductions and either local or global atrophy in aMCI. In addition, a logistic regression model which combined task deactivation reductions and atrophy in parietal DMN regions showed higher classificatory accuracy of aMCI than separate task deactivation or atrophy models. Results suggest that task deactivation reductions and atrophy in parietal regions provide complementary rather than redundant information in aMCI. Future longitudinal studies will be required to assess the utility of combining task deactivation reductions and atrophy in the detection of early AD. PMID:21860094

  15. THE PROJECT-X INJECTOR EXPERIMENT: A NOVEL HIGH PERFORMANCE FRONT-END FOR A FUTURE HIGH POWER PROTON FACILITY AT FERMILAB

    SciTech Connect

    Nagaitsev, S.; et al,

    2013-09-25

    A multi-MW proton facility, Project X, has been proposed and is currently under development at Fermilab. We are carrying out a program of research and development aimed at integrated systems testing of critical components comprising the front end of Project X. This program, known as the Project X Injector Experiment (PXIE), is being undertaken as a key component of the larger Project X R&D program. The successful completion of this program will validate the concept for the Project X front end, thereby minimizing a primary technical risk element within Project X. PXIE is currently under construction at Fermilab and will be completed over the period FY12-17. PXIE will include an H* ion source, a CW 2.1-MeV RFQ and two superconductive RF (SRF) cryomodules providing up to 25 MeV energy gain at an average beam current of 1 mA (upgradable to 2 mA). Successful systems testing will also demonstrate the viability of novel front end technologies that are expected find applications beyond Project X.

  16. Computer software design description for the Treated Effluent Disposal Facility (TEDF), Project L-045H, Operator Training Station (OTS)

    SciTech Connect

    Carter, R.L. Jr.

    1994-11-07

    The Treated Effluent Disposal Facility (TEDF) Operator Training Station (OTS) is a computer-based training tool designed to aid plant operations and engineering staff in familiarizing themselves with the TEDF Central Control System (CCS).

  17. High Purity Germanium Gamma-PHA Assay of Uranium Storage Pigs for 321-M Facility

    SciTech Connect

    Dewberry, R.A.

    2001-09-18

    The Analytical Development Section of SRTC was requested by the Facilities Disposition Division (FDD) to determine the holdup of enriched uranium in the 321-M facility as part of an overall deactivation project of the facility. The 321-M facility was used to fabricate enriched uranium fuel assemblies, lithium-aluminum target tubes, neptunium assemblies, and miscellaneous components for the production reactors. The facility also includes the 324-M storage building and the passageway connecting it to 321-M. The results of the holdup assays are essential for determining compliance with the Solid Waste's Waste Acceptance Criteria, Material Control and Accountability, and to meet criticality safety controls. This report describes and documents the use of a portable HPGe detector and EG and G Dart system that contains a high voltage power supply, signal processing electronics, a personal computer with Gamma-Vision software, and space to store and manipulate multiple 4096-channel g-ray spectra to assay for 235U content in 268 uranium shipping and storage pigs. This report includes a description of three efficiency calibration configurations and also the results of the assay. A description of the quality control checks is included as well.

  18. High Purity Germanium Gamma-PHA Assay of Uranium Scrap Cans Used in 321-M Facility

    NASA Astrophysics Data System (ADS)

    Salaymeh, S. R.; Dewberry, R. A.; Casella, V.

    2001-12-01

    The Analytical Development Section of SRTC was requested by the Facilities Disposition Division (FDD) to determine the holdup of enriched uranium in the 321-M facility as part of an overall deactivation project of the facility. The 321-M facility was used to fabricate enriched uranium fuel assemblies, lithium-aluminum target tubes, neptunium assemblies, and miscellaneous components for the production reactors. The facility also includes the 324-M storage building and the passageway connecting it to 321-M. The results of the holdup assays are essential for determining compliance with the Solid Waste's Waste Acceptance Criteria, Material Control & Accountability, and to meet criticality safety controls. This report describes and documents the use of a portable HPGe detector and EG&G DART system that contains a high voltage power supply, signal processing electronics, a personal computer with Gamma-Vision software, and space to store and manipulate multiple 4096-channel gamma-ray spectra to assay for 235U content. The system was used to assay a large number of scrap cans used to store highly enriched uranium (HEU) chips and filings. This report includes a description of two efficiency calibration configurations and also the results of the assay. A description of the quality control checks is included as well.

  19. Fast Flux Test Facility (FFTF) standby plan

    SciTech Connect

    Hulvey, R.K.

    1997-03-06

    The FFTF Standby Plan, Revision 0, provides changes to the major elements and project baselines to maintain the FFTF plant in a standby condition and to continue washing sodium from irradiated reactor fuel. The Plan is consistent with the Memorandum of Decision approved by the Secretary of Energy on January 17, 1997, which directed that FFTF be maintained in a standby condition to permit the Department to make a decision on whether the facility should play a future role in the Department of Energy`s dual track tritium production strategy. This decision would be made in parallel with the intended December 1998 decision on the selection of the primary, long- term source of tritium. This also allows the Department to review the economic and technical feasibility of using the FFTF to produce isotopes for the medical community. Formal direction has been received from DOE-RL and Fluor 2020 Daniel Hanford to implement the FFTF standby decision. The objective of the Plan is maintain the condition of the FFTF systems, equipment and personnel to preserve the option for plant restart within three and one-half years of a decision to restart, while continuing deactivation work which is consistent with the standby mode.

  20. Differential Deactivation during Mentalizing and Classification of Autism Based on Default Mode Network Connectivity

    PubMed Central

    Murdaugh, Donna L.; Shinkareva, Svetlana V.; Deshpande, Hrishikesh R.; Wang, Jing; Pennick, Mark R.; Kana, Rajesh K.

    2012-01-01

    The default mode network (DMN) is a collection of brain areas found to be consistently deactivated during task performance. Previous neuroimaging studies of resting state have revealed reduced task-related deactivation of this network in autism. We investigated the DMN in 13 high-functioning adults with autism spectrum disorders (ASD) and 14 typically developing control participants during three fMRI studies (two language tasks and a Theory-of-Mind (ToM) task). Each study had separate blocks of fixation/resting baseline. The data from the task blocks and fixation blocks were collated to examine deactivation and functional connectivity. Deficits in the deactivation of the DMN in individuals with ASD were specific only to the ToM task, with no group differences in deactivation during the language tasks or a combined language and self-other discrimination task. During rest blocks following the ToM task, the ASD group showed less deactivation than the control group in a number of DMN regions, including medial prefrontal cortex (MPFC), anterior cingulate cortex, and posterior cingulate gyrus/precuneus. In addition, we found weaker functional connectivity of the MPFC in individuals with ASD compared to controls. Furthermore, we were able to reliably classify participants into ASD or typically developing control groups based on both the whole-brain and seed-based connectivity patterns with accuracy up to 96.3%. These findings indicate that deactivation and connectivity of the DMN were altered in individuals with ASD. In addition, these findings suggest that the deficits in DMN connectivity could be a neural signature that can be used for classifying an individual as belonging to the ASD group. PMID:23185536

  1. Mixed and Low-Level Waste Treatment Facility project. Executive summary: Volume 1, Program summary information; Volume 2, Waste stream technical summary: Draft

    SciTech Connect

    Not Available

    1992-04-01

    Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. The engineering studies, initiated in July 1991, identified 37 mixed waste streams, and 55 low-level waste streams. This report documents the waste stream information and potential treatment strategies, as well as the regulatory requirements for the Department of Energy-owned treatment facility option. The total report comprises three volumes and two appendices. This report consists of Volume 1, which explains the overall program mission, the guiding assumptions for the engineering studies, and summarizes the waste stream and regulatory information, and Volume 2, the Waste Stream Technical Summary which, encompasses the studies conducted to identify the INEL`s waste streams and their potential treatment strategies.

  2. Spent nuclear fuel project cold vacuum drying facility tempered water and tempered water cooling system design description

    SciTech Connect

    IRWIN, J.J.

    1998-11-30

    This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Tempered Water (TW) and Tempered Water Cooling (TWC) System . The SDD was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-O02, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the TW and TWC equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SOD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

  3. SOLERAS - Solar Controlled Environment Agriculture Project. Final report, Volume 7. Science Applications, Incorporated field test facility preliminary design

    SciTech Connect

    Not Available

    1985-01-01

    This report contains the preliminary design of an SCEAS Engineering Test Facility (ETF). The ETF is a 3600 m/sup 2/ fluid roof greenhouse with an inflated plastic film roof to maintain a clean environment for the fluid roof and to protect the inner glazing from hail and other small missiles. The objective of the design was the faithful scaling of the commercial facility to ensure that the ETF results could be extrapolated to a commercial facility of any size. Therefore, all major features, including the photovoltaic power system, an integral water desalination system and even the basic structural module have been retained. The design is described in substantial detail in the body of this report, with appendices giving the drawings and specifications.

  4. Deactivation of Ni2P/SiO2 catalyst in hydrodechlorination of chlorobenzene

    NASA Astrophysics Data System (ADS)

    Chen, Jixiang; Ci, Donghui; Yang, Qing; Li, Kelun

    2014-11-01

    The deactivation of the Ni2P/SiO2 catalyst in the hydrodechlorination of chlorobenzene was studied. To better illuminate the reasons for the deactivation, the effect of HCl on the structure and activity of Ni2P/SiO2 was investigated. For comparison, the deactivation of the Ni/SiO2 catalyst was also involved. It was found that the Ni2P particles possessed good resistance to HCl poison and to sintering, which is ascribed to the electron-deficiency of Niδ+(0 < δ < 1) site in Ni2P. Acted as the Lewis and Brönsted acid site, the Niδ+ site and the Psbnd OH group on Ni2P/SiO2 catalyzed the formation of the carbonaceous deposit that was difficultly eliminated by hydrogenation. The carbonaceous deposit covered the active sites and might also induce a decrease in the Ni2P crystallinity, subsequently leading to the Ni2P/SiO2 deactivation. Different from Ni2P/SiO2, Ni/SiO2 was mainly deactivated by the chlorine poison and the sintering of nickel crystallites.

  5. A model for the recovery kinetics of rod phototransduction, based on the enzymatic deactivation of rhodopsin.

    PubMed Central

    Laitko, U; Hofmann, K P

    1998-01-01

    We propose a model for the recovery of the retinal rod photoresponse after a short stimulus. The approach describes the enzymatic deactivation of the photoactivated receptor, rhodopsin, by simple enzyme kinetics. An important feature of this description is that the R* deactivation obeys different time laws, depending on the numbers of R* formed per disc membrane and available enzyme molecules. If the enzyme works below substrate saturation, the rate of deactivation depends linearly on the number of R*, whereas for substrate saturation a hyperbolic relation--the well-known Michaelis-Menten equation--applies. This dichotomy is used to explain experimental finding that the relation between the saturation time of the photoresponse after short illumination and the flash strength has two sharply separated branches for low and high flash intensities (up to approximately 10% bleaching). By relating both branches to properties of the enzymatic rhodopsin deactivation, the new model transcends the classical notion of a constant characteristic lifetime of activated rhodopsin. With parameters that are plausible in the light of the available data and the additional information that the deactivating enzyme, rhodopsin kinase, and the signaling G-protein, transducin, compete for the active receptor, the slopes of the saturation function are correctly reproduced. PMID:9533693

  6. Spread of activation and deactivation in the brain: does age matter?

    PubMed Central

    Gordon, Brian A.; Tse, Chun-Yu; Gratton, Gabriele; Fabiani, Monica

    2014-01-01

    Cross-sectional aging functional MRI results are sometimes difficult to interpret, as standard measures of activation and deactivation may confound variations in signal amplitude and spread, which however, may be differentially affected by age-related changes in various anatomical and physiological factors. To disentangle these two types of measures, here we propose a novel method to obtain independent estimates of the peak amplitude and spread of the BOLD signal in areas activated (task-positive) and deactivated (task-negative) by a Sternberg task, in 14 younger and 28 older adults. The peak measures indicated that, compared to younger adults, older adults had increased activation of the task-positive network, but similar levels of deactivation in the task-negative network. Measures of signal spread revealed that older adults had an increased spread of activation in task-positive areas, but a starkly reduced spread of deactivation in task-negative areas. These effects were consistent across regions within each network. Further, there was greater variability in the anatomical localization of peak points in older adults, leading to reduced cross-subject overlap. These results reveal factors that may confound the interpretation of studies of aging. Additionally, spread measures may be linked to local connectivity phenomena and could be particularly useful to analyze age-related deactivation patterns, complementing the results obtained with standard peak and region of interest analyses. PMID:25360115

  7. RCRA (Resource Conservation and Recovery Act of 1976) ground-water monitoring projects for Hanford facilities: Progress report, October 1--December 31, 1988: Volume 1, Text

    SciTech Connect

    Fruland, R.M.; Bates, D.J.; Lundgren, R.E.

    1989-04-01

    This report describes the progress of 13 Hanford ground-water monitoring projects for the period October 1 to December 31, 1988. There are 16 individual hazardous waste facilities covered by the 13 ground-water monitoring projects. The Grout Treatment Facility is included in this series of quarterly reports for the first time. The 13 projects discussed in this report were designed according to applicable interim-status ground-water monitoring requirements specified in the Resource Conservation and Recovery Act of 1976 (RCRA). During this quarter, field activities primarily consisted of sampling and analyses, and water-level monitoring. The 200 Areas Low-Level Burial Grounds section includes sediment analyses in addition to ground-water monitoring results. Twelve new wells were installed during the previous quarter: two at the 216-A-29 Ditch, six at the 216-A-10 Crib, and four at the 216-B-3 Pond. Preliminary characterization data for these new wells include drillers' logs and other drilling and site characterization data, and are provided in Volume 2 or on microfiche in the back of Volume 1. 26 refs., 28 figs., 74 tabs.

  8. The Current Status of the Space Station Biological Research Project: a Core Facility Enabling Multi-Generational Studies under Slectable Gravity Levels

    NASA Astrophysics Data System (ADS)

    Santos, O.

    2002-01-01

    The Space Station Biological Research Project (SSBRP) has developed a new plan which greatly reduces the development costs required to complete the facility. This new plan retains core capabilities while allowing for future growth. The most important piece of equipment required for quality biological research, the 2.5 meter diameter centrifuge capable of accommodating research specimen habitats at simulated gravity levels ranging from microgravity to 2.0 g, is being developed by NASDA, the Japanese space agency, for the SSBRP. This is scheduled for flight to the ISS in 2007. The project is also developing a multi-purpose incubator, an automated cell culture unit, and two microgravity habitat holding racks, currently scheduled for launch in 2005. In addition the Canadian Space Agency is developing for the project an insect habitat, which houses Drosophila melanogaster, and provides an internal centrifuge for 1 g controls. NASDA is also developing for the project a glovebox for the contained manipulation and analysis of biological specimens, scheduled for launch in 2006. This core facility will allow for experimentation on small plants (Arabidopsis species), nematode worms (C. elegans), fruit flies (Drosophila melanogaster), and a variety of microorganisms, bacteria, yeast, and mammalian cells. We propose a plan for early utilization which focuses on surveys of changes in gene expression and protein structure due to the space flight environment. In the future, the project is looking to continue development of a rodent habitat and a plant habitat that can be accommodated on the 2.5 meter centrifuge. By utilizing the early phases of the ISS to broadly answer what changes occur at the genetic and protein level of cells and organisms exposed to the ISS low earth orbit environment, we can generate interest for future experiments when the ISS capabilities allow for direct manipulation and intervention of experiments. The ISS continues to hold promise for high quality, long

  9. School Capital Manual. An Interim Guide for School Boards, Administrators, Facility Planners and Consultants Who Engage in School Building Projects.

    ERIC Educational Resources Information Center

    Alberta Dept. of Education, Edmonton.

    This manual is intended for use by the Alberta, Canada, school boards, administrators, consultants, education staff, and other individuals involved in school building projects. The purpose of the School Capital Plan, funding, and Alberta Education's funding framework are detailed. The school building project components of the School Capital Plan…

  10. Developmental Handicaps: Prevention and Treatment, II. A Cooperative Project between University Affiliated Facilities and State MCH/CC Programs.

    ERIC Educational Resources Information Center

    John F. Kennedy Inst., Baltimore, MD.

    Second in a series of three publications which address the prevention and treatment of developmental handicaps, the volume continues the effort to expand working relationships among university affiliated facilities (UAFs) and Title V Maternal and Child Health Programs. Five papers in Section I address developmental issues as of 1984: "Prenatal…

  11. 25 CFR 700.459 - Assistance for demonstration projects and for provision of related facilities and services.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... of related facilities and services. 700.459 Section 700.459 Indians THE OFFICE OF NAVAJO AND HOPI... governments, the Navajo and Hopi Tribes, tribal chapters, profit and nonprofit organizations, and individuals... under this section for the purpose of undertaking a technical feasibility study of a...

  12. 25 CFR 700.459 - Assistance for demonstration projects and for provision of related facilities and services.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... of related facilities and services. 700.459 Section 700.459 Indians THE OFFICE OF NAVAJO AND HOPI... governments, the Navajo and Hopi Tribes, tribal chapters, profit and nonprofit organizations, and individuals... under this section for the purpose of undertaking a technical feasibility study of a...

  13. 25 CFR 700.459 - Assistance for demonstration projects and for provision of related facilities and services.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... of related facilities and services. 700.459 Section 700.459 Indians THE OFFICE OF NAVAJO AND HOPI... governments, the Navajo and Hopi Tribes, tribal chapters, profit and nonprofit organizations, and individuals... under this section for the purpose of undertaking a technical feasibility study of a...

  14. 25 CFR 700.459 - Assistance for demonstration projects and for provision of related facilities and services.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... of related facilities and services. 700.459 Section 700.459 Indians THE OFFICE OF NAVAJO AND HOPI... governments, the Navajo and Hopi Tribes, tribal chapters, profit and nonprofit organizations, and individuals... under this section for the purpose of undertaking a technical feasibility study of a...

  15. 25 CFR 700.459 - Assistance for demonstration projects and for provision of related facilities and services.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... of related facilities and services. 700.459 Section 700.459 Indians THE OFFICE OF NAVAJO AND HOPI... governments, the Navajo and Hopi Tribes, tribal chapters, profit and nonprofit organizations, and individuals... under this section for the purpose of undertaking a technical feasibility study of a...

  16. Developmental Handicaps: Prevention and Treatment, III. A Cooperative Project between University Affiliated Facilities and State MCH/CC Programs.

    ERIC Educational Resources Information Center

    John F. Kennedy Inst., Baltimore, MD.

    Third in a series on the prevention and treatment of developmental handicaps, this publication focuses on linkages among the network of university affiliated facilities (UAFs) and Title V Maternal and Child Health Programs. Four papers in Section I address the following developmental issues as of 1985: "Serious Viral Infection in Developmentally…

  17. Case Studies of Potential Facility-Scale and Utility-Scale Non-Hydro Renewable Energy Projects across Reclamation

    SciTech Connect

    Haase, S.; Burman, K.; Dahle, D.; Heimiller, D.; Jimenez, A.; Melius, J.; Stoltenberg, B.; VanGeet, O.

    2013-05-01

    This report summarizes the results of an assessment and analysis of renewable energy opportunities conducted for the U.S. Department of the Interior, Bureau of Reclamation by the National Renewable Energy Laboratory. Tasks included assessing the suitability for wind and solar on both a utility and facility scale.

  18. Technical assistance to Ohio closure sites; Technologies to address leachate from the on-site disposal facility at Fernald Environmental Management Project, Ohio

    SciTech Connect

    Hazen, Terry

    2002-08-26

    On August 6-7, 2002, a Technical Assistance Team (''Team'') from the U.S. Department of Energy (DOE) Subsurface Contaminants Focus Area (SCFA) met with Fernald Environmental Management Project (FEMP) personnel in Ohio to assess approaches to remediating uranium-contaminated leachate from the On-Site Disposal Facility (OSDF). The Team was composed of technical experts from national labs, technology centers, and industry and was assembled in response to a request from the FEMP Aquifer Restoration Project. Dave Brettschneider of Fluor Fernald, Inc., requested that a Team of experts be convened to review technologies for the removal of uranium in both brine ion exchange regeneration solution from the Advanced Wastewater Treatment facility and in the leachate from the OSDF. The Team was asked to identify one or more technologies for bench-scale testing as a cost effective alternative to remove uranium so that the brine regeneration solution from the Advanced Waste Water Treatment facility and the leachate from the OSDF can be discharged without further treatment. The Team was also requested to prepare a recommended development and demonstration plan for the alternative technologies. Finally, the Team was asked to make recommendations on the optimal technical solution for field implementation. The Site's expected outcomes for this effort are schedule acceleration, cost reduction, and better long-term stewardship implementation. To facilitate consideration of the most appropriate technologies, the Team was divided into two groups to consider the brine and the leachate separately, since they represent different sources with different constraints on solutions, e.g., short-term versus very long-term and concentrated versus dilute contaminant matrices. This report focuses on the technologies that are most appropriate for the leachate from the OSDF. Upon arriving at FEMP, project personnel asked the Team to concentrate its efforts on evaluating potential technologies and

  19. American Recovery and Reinvestment Act ( ARRA) FEMP Technical Assistance, U.S. General Services Administration - Project 194 U.S. Custom Cargo Inspection Facility, Detroit, MI

    SciTech Connect

    Arends, J.; Sandusky, William F.

    2010-05-31

    This report documents the findings of an on-site audit of the U.S. Customs Cargo Inspection Facility (CIF) in Detroit, Michigan. The federal landlord for this building is the General Services Administration (GSA). The focus of the audit was to identify various no-cost or low-cost energy-efficiency opportunities that, once implemented, would reduce electrical and gas consumption and increase the operational efficiency of the building. This audit also provided an opportunity to identify potential capital cost projects that should be considered in the future to acquire additional energy (electric and gas) and water savings to further increase the operational efficiency of the building.

  20. Highly controlled nest homeostasis of honey bees helps deactivate phenolics in nectar

    NASA Astrophysics Data System (ADS)

    Liu, Fanglin; He, Jianzhong; Fu, Wenjun

    2005-06-01

    Honey bees have a highly developed nest homeostasis, for example, maintaining low CO2 levels and stable nest temperatures at 35°C.We investigate the role of nest homeostasis in deactivating phenolic compounds present in the nectar of Aloe littoralis. We show that the phenolic content in nectar was reduced (from 0.65% to 0.49%) after nectar was incubated in a nest of Apis cerana, and that it was reduced still more (from 0.65% to 0.37%) if nectar was mixed with hypopharyngeal gland proteins (HGP) of worker bees before being placed inside a nest. HGP had little effect on samples outside a nest, indicating that nest conditions are necessary for HGP to deactivate phenolics in nectar. Consequently, the highly controlled nest homeostasis of honey bees facilitates direct deactivation of phenolics in nectar, and plays a role in the action of HGP as well.