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Sample records for facilities deactivating project

  1. Isotopes facilities deactivation project at Oak Ridge National Laboratory

    SciTech Connect

    Eversole, R.E.

    1997-05-01

    The production and distribution of radioisotopes for medical, scientific, and industrial applications has been a major activity at Oak Ridge National Laboratory (ORNL) since the late 1940s. As the demand for many of these isotopes grew and their sale became profitable, the technology for the production of the isotopes was transferred to private industry, and thus, many of the production facilities at ORNL became underutilized. In 1989, the U.S. Department of Energy (DOE) instructed ORNL to identify and prepare various isotopes production facilities for safe shutdown. In response, ORNL identified 19 candidate facilities for shutdown and established the Isotopes Facilities Shutdown Program. In 1993, responsibility for the program was transitioned from the DOE Office of Nuclear Energy to the DOE Office of Environmental Management and Uranium Enrichment Operation`s Office of Facility Transition and Management. The program was retitled the Isotopes Facilities Deactivation Project (IFDP), and implementation responsibility was transferred from ORNL to the Lockheed Martin Energy Systems, Inc. (LMES), Environmental Restoration (ER) Program.

  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. Implementing RCRA during facility deactivation

    SciTech Connect

    Lebaron, G.J.

    1997-09-07

    RCRA regulations require closure of permitted treatment, storage and disposal (TSD) facilities within 180 days after cessation of operations, and this may essentially necessitate decommissioning to complete closure. A more cost effective way to handle the facility would be to significantly reduce the risk to human health and the environment by taking it from its operational status to a passive, safe, inexpensive-to-maintain surveillance and maintenance condition (deactivation) prior to decommissioning. This paper presents an innovative approach to the cost effective deactivation of a large, complex chemical processing facility permitted under RCRA. The approach takes into account risks to the environment posed by this facility in comparison to risks posed by neighboring facilities at the site. The paper addresses the manner in which: 1) stakeholders and regulators were involved; 2) identifies a process by which the project proceeds and regulators and stakeholders were involved; 3) end points were developed so completion of deactivation was clearly identified at the beginning of the project, and 4) innovative practices were used to deactivate more quickly and cost effectively.

  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. 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.

  8. 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).

  9. 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.

  10. 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.

  11. Deactivating a major nuclear fuels reprocessing facility cost effectively

    SciTech Connect

    LeBaron, G.J.

    1997-08-15

    This paper describes three key processes used in deactivating the Plutonium Uranium Extraction (PUREX) Facility, a large, complex nuclear reprocessing facility, 15 months ahead of schedule and $77 million under budget. The organization was reengineered to refine its business processes and more effectively organize around the deactivation work scope. Multi-disciplined work teams were formed to be self-sufficient and empowered to make decisions and perform work. A number of benefits were realized by reengineering. A comprehensive process to develop end points which clearly identified specific results and the post-project facility configuration was developed so all areas of a facility were addressed. Clear and specific end points allowed teams to focus on completing deactivation activities and helped ensure there were no unfulfilled end-of-project expectations. The RCRA regulations require closure of permitted facilities within 180 days after cessation of operations which may essentially necessitate decommissioning. A more cost effective approach was adopted which significantly reduced risk to human health and the environment by taking the facility to a passive, safe, inexpensive-to-maintain surveillance and maintenance condition (deactivation) prior to disposition. PUREX thus became the first large reprocessing facility with active TSD [treatment, storage, and disposal] units to be deactivated under the RCRA regulations.

  12. 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).

  13. PFP deactivation project management plan

    SciTech Connect

    Bogen, D.M.

    1997-07-28

    This document identifies the overall approach for deactivation of the Plutonium Finishing Plant (PFP) Complex, excluding the vaults, and includes a draft set of End Point Criteria for all buildings being deactivated.

  14. 49 CFR 192.727 - Abandonment or deactivation of facilities.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 3 2011-10-01 2011-10-01 false Abandonment or deactivation of facilities. 192.727... Abandonment or deactivation of facilities. (a) Each operator shall conduct abandonment or deactivation of... commercially navigable waterway, the last operator of that facility must file a report upon abandonment of...

  15. 49 CFR 192.727 - Abandonment or deactivation of facilities.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 49 Transportation 3 2014-10-01 2014-10-01 false Abandonment or deactivation of facilities. 192.727... Abandonment or deactivation of facilities. (a) Each operator shall conduct abandonment or deactivation of... commercially navigable waterway, the last operator of that facility must file a report upon abandonment of...

  16. 49 CFR 192.727 - Abandonment or deactivation of facilities.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 49 Transportation 3 2012-10-01 2012-10-01 false Abandonment or deactivation of facilities. 192.727... Abandonment or deactivation of facilities. (a) Each operator shall conduct abandonment or deactivation of... commercially navigable waterway, the last operator of that facility must file a report upon abandonment of...

  17. 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... Abandonment or deactivation of facilities. (a) Each operator shall conduct abandonment or deactivation of... commercially navigable waterway, the last operator of that facility must file a report upon abandonment of...

  18. 49 CFR 195.59 - 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. 195.59... Abandonment or deactivation of facilities. For each abandoned offshore pipeline facility or each abandoned... operator of that facility must file a report upon abandonment of that facility. (a) The preferred method...

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

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 49 Transportation 3 2012-10-01 2012-10-01 false Abandonment or deactivation of facilities. 195.59... Abandonment or deactivation of facilities. For each abandoned offshore pipeline facility or each abandoned... operator of that facility must file a report upon abandonment of that facility. (a) The preferred method...

  20. 49 CFR 195.59 - Abandonment or deactivation of facilities.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 49 Transportation 3 2014-10-01 2014-10-01 false Abandonment or deactivation of facilities. 195.59... Abandonment or deactivation of facilities. For each abandoned offshore pipeline facility or each abandoned... operator of that facility must file a report upon abandonment of that facility. (a) The preferred method...

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

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 3 2011-10-01 2011-10-01 false Abandonment or deactivation of facilities. 195.59... Abandonment or deactivation of facilities. For each abandoned offshore pipeline facility or each abandoned... operator of that facility must file a report upon abandonment of that facility. (a) The preferred method...

  2. 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.

  3. 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

  4. 340 Waste handling facility deactivation plan

    SciTech Connect

    Stordeur, R.T., Westinghouse Hanford

    1996-12-27

    This document provides an overview of both the present status of the 340 Complex (within Hanford`s 300 Area), and of tasks associated with the deactivation of segments associated with radioactive, mixed liquid waste receipt, storage, and shipping. The plan also describes activities that will allow portions of the 340 Complex to remain in service.

  5. 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.

  6. 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

  7. 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.

  8. 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.

  9. 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.

  10. 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

  11. 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.

  12. 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

  13. 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.

  14. 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.

  15. Falls related to accidental deactivation of deep brain stimulators in patients with Parkinson's disease living in long term care facilities.

    PubMed

    Tousi, Babak; Wilson, Kathy

    2013-01-01

    This case series highlights three patients with Parkinson's disease residing at nursing home facilities whose deep brain stimulators were accidentally deactivated for varying lengths of time, which was associated with an increase in falls. In all three cases, neither the patients nor the caregivers were aware of the random deactivations/reactivations. We propose a specific care plan for these patients that includes further education of caregivers regarding deep brain stimulators and regular checks of the review device, especially when there is concern about a patient's mobility or balance that is out of character.

  16. 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

  17. 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.

  18. 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.

  19. 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

  20. 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

  1. 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.

  2. 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.

  3. 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.

  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. 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.

  8. 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.

  9. Campania Region's Educational Quality Facilities Project

    ERIC Educational Resources Information Center

    Ponti, Giorgio

    2009-01-01

    This article describes the Educational Quality Facilities project undertaken by Italy's Campania Region to provide quality facilities to all of its communities basing new spaces on the "Flexible Learning Module". The objectives of the five-year project are to: build and equip new educational spaces; improve the quality of existing buildings and…

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. Data quality objectives for PUREX deactivation flushing

    SciTech Connect

    Bhatia, R.K.

    1995-04-01

    This Data Quality Objection (DQO) defines the sampling and analysis requirements necessary to support the deactivation of the Plutonium-Uranium Extraction (PUREX) facility vessels that are regulated by WAC 173-303. Specifically, sampling and analysis requirements are identified for the flushing operations that are a major element of PUREX deactivation.

  15. 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.

  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. Final deactivation report on the radioisotope area services, Building 3034, 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. 3034, after completion of deactivation activities as outlined by the Department of Energy 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 Department of Energy Office of Environmental Restoration (EM-40) Program. This report provides a history and profile of Bldg. 3034 before commencement of 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, an supporting documentation provided in the Office of Nuclear Materials and Facility Stabilization Program (EM-60) Turnover Package, are discussed. Building 3034 will require access to facilitate required surveillance and maintenance (S&M) activities to maintain the building safety envelope. Building 3034 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. In addition to the minimal S&M activities, the building will be occupied by the maintenance coordinator and the S&M supervisor for the Isotopes Facilities Deactivation Project. The exterior doors are locked when unoccupied to prevent unauthorized access. All materials have been removed from the building. Piping and alarms have been deactivated.

  18. 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…

  19. VOCATIONAL-TECHNICAL FACILITIES PROJECT. PROGRESS REPORT.

    ERIC Educational Resources Information Center

    CONRAD, M.J.; VALENTINE, I.E.

    IN THE FIRST PHASE OF A PROJECT FOR DEVELOPING PLANNING GUIDES FOR VOCATIONAL FACILITIES, THE OVERALL DIRECTION OF A SERIES OF PLANNING GUIDES IS BEING DETERMINED. IN THE SECOND PHASE AT LEAST ONE PLANNING MANUAL WILL BE DEVELOPED TO SERVE AS A MODEL FOR THE FULL SERIES. A LOCAL WORKING GROUP COMPOSED OF THREE SPECIALISTS FROM THE CENTER FOR…

  20. 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.

  1. 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.

  2. 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.

  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. National Ignition Facility Project Site Safety Program

    SciTech Connect

    Moses, E

    2001-09-30

    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 the construction, equipment installation, and commissioning activities. As the NIF Project transitions from a conventional facility construction activity to one of equipment installation, commissioning, initial laser operations, and other more routine-like operations, new safety requirements are needed. The NIF Project Site Safety Program (NPSSP) requires that all 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. More specific requirements for construction activities under the Integration Management and Installation (IMI) contract are provided in the ''NIF Infrastructure Health and Safety Plan'', subtier to this program. Specifically this document: Defines the fundamental NIF site safety philosophy, Defines the areas covered by this safety program (see Appendix B), Identifies management roles and responsibilities, Defines core safety management processes, and Identifies NIF site-specific safety requirements.

  5. 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)

  6. 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.

  7. 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.

  8. 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.

  9. 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

  10. Plutonium Reclamation Facility incident response project progress report

    SciTech Connect

    Austin, B.A.

    1997-11-25

    This report provides status of Hanford activities in response to process deficiencies highlighted during and in response to the May 14, 1997, explosion at the Plutonium Reclamation Facility. This report provides specific response to the August 4, 1997, memorandum from the Secretary which requested a progress report, in 120 days, on activities associated with reassessing the known and evaluating new vulnerabilities (chemical and radiological) at facilities that have been shut down, are in standby, are being deactivated or have otherwise changed their conventional mode of operation in the last several years. In addition, this report is intended to provide status on emergency response corrective activities as requested in the memorandum from the Secretary on August 28, 1997. Status is also included for actions requested in the second August 28, 1997, memorandum from the Secretary, regarding timely notification of emergencies.

  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. 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

  13. 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.

  14. 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.

  15. 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.

  16. Deactivation of Building 7602

    SciTech Connect

    Yook, H.R.; Barnett, J.R.; Collins, T.L.

    1995-10-01

    The Department of Energy (DOE) has sponsored research and development programs in Building 7602 at Oak Ridge National Laboratory (ORNL) since 1984. This work focused on development of advanced technology for processing nuclear fuels. Building 7602 was used for engineering-scale tests using depleted and natural uranium to simulate the nuclear fuel. In April 1994 the DOE Office of Nuclear Energy (NE) sent supplemental FY 1994 guidance to ORNL stating that in FY 1995 and beyond, Building 7602 is considered surplus to NE programs and missions and shall be shut down (deactivated) and maintained in a radiologically and industrially safe condition with minimal surveillance and maintenance (S&M). DOE-NE subsequently provided FY 1995 funding to support the deactivation activities. Deactivation of Building 7602 was initiated on October 1, 1994. The principal activity during the first quarter of FY 1995 was removal of process materials (chemicals and uranium) from the systems. The process systems were operated to achieve chemical solution concentrations needed for reuse or disposal of the solutions prior to removal of the materials from the systems. During this phase of deactivation the process materials processed and removed were: (1) Uranyl nitrate solution 30,178 L containing 4490 kg of uranium; (2) Nitric acid (neutralized) 9850 L containing less than 0.013 kg of uranium; (3) Organic solution 3346 L containing 265 kg of uranium; (4) Uranium oxide powder 95 kg; and (5) Miscellaneous chemicals. At the end of December 1994, the process systems and control systems were shut down and deactivated. Disposition of the process materials removed from the process systems in Building 7602 proved to be the most difficult part of the deactivation. An operational stand down and funding reductions at Y-12 prevented planned conversion of the uranyl nitrate solution to depleted uranium oxide powder. This led to disposal of the uranyl nitrate solution as waste.

  17. 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.

  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. FACILITY 734, SOUTHEAST SIDE, SHOWING FIREPLACE AND DINING ROOM PROJECTION, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    FACILITY 734, SOUTHEAST SIDE, SHOWING FIREPLACE AND DINING ROOM PROJECTION, OBLIQUE VIEW FACING NORTH-NORTHWEST. - Schofield Barracks Military Reservation, Central-Entry Single-Family Housing Type, Between Bragg & Grime Streets near Ayres Avenue, Wahiawa, Honolulu County, HI

  20. Ethanol Production from Biomass: Large Scale Facility Design Project

    SciTech Connect

    Berson, R. Eric

    2009-10-29

    High solids processing of biomass slurries provides the following benefits: maximized product concentration in the fermentable sugar stream, reduced water usage, and reduced reactor size. However, high solids processing poses mixing and heat transfer problems above about 15% for pretreated corn stover solids due to their high viscosities. Also, highly viscous slurries require high power consumption in conventional stirred tanks since they must be run at high rotational speeds to maintain proper mixing. An 8 liter scraped surface bio-reactor (SSBR) is employed here that is designed to efficiently handle high solids loadings for enzymatic saccharification of pretreated corn stover (PCS) while maintaining power requirements on the order of low viscous liquids in conventional stirred tanks. Saccharification of biomass exhibit slow reaction rates and incomplete conversion, which may be attributed to enzyme deactivation and loss of activity due to a variety of mechanisms. Enzyme deactivation is classified into two categories here: one, deactivation due to enzyme-substrate interactions and two, deactivation due to all other factors that are grouped together and termed “non-specific” deactivation. A study was conducted to investigate the relative extents of “non-specific” deactivation and deactivation due to “enzyme-substrate interactions” and a model was developed that describes the kinetics of cellulose hydrolysis by considering the observed deactivation effects. Enzyme substrate interactions had a much more significant effect on overall deactivation with a deactivation rate constant about 20X higher than the non-specific deactivation rate constant (0.35 h-1 vs 0.018 h-1). The model is well validated by the experimental data and predicts complete conversion of cellulose within 30 hours in the absence of enzyme substrate interactions.

  1. 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.

  2. 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.

  3. 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.

  4. The Muon Science Facility at the JKJ Project

    NASA Astrophysics Data System (ADS)

    Miyake, Y.; Nishiyama, K.; Sakamoto, S.; Shimomura, K.; Kadono, R.; Higemoto, W.; Fukuchi, K.; Makimura, S.; Beveridge, J. L.; Ishida, K.; Matsuzaki, T.; Watanabe, I.; Matsuda, Y.; Kawamura, N.; Nagamine, K.

    2001-12-01

    The muon science facility is one of the experimental arenas of the JKJ project, which was recently approved for construction in a period from 2001 to 2006, as well as neutron science, particle and nuclear physics, neutrino physics and nuclear transmutation science. The muon science experimental area is planned to be located in the integrated building of the facility for the materials and life science study. One muon target will be installed upstream of the neutron target in a period of phase 1. The beam line and facility are designed to allow the later installation of a 2nd muon target in a more upstream location. The detailed design for electricity, cooling water, primary proton beam line, one muon target and secondary beam lines (a superconducting solenoid decay muon channel, a dedicated surface muon channel, and an ultra slow muon channel) is underway. In the symposium, a latest status of the muon science facility at JKJ project will be reported.

  5. 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.

  6. 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.

  7. Educational Facility Design and Project Based Learning: "The Real Connection"

    ERIC Educational Resources Information Center

    Schrader, David L.; Sole, John

    2009-01-01

    There is a case to be made for the integration of the Project Based Service Learning (PBSL) process and the design and construction of educational facilities. A growing body of research supports the notion that the formulaic educational system of the last hundred years may no longer serve the learning styles of new and future generations. Their…

  8. Implementation of a secure multi-project laboratory facility

    NASA Astrophysics Data System (ADS)

    Draffin, David M.; Bacha, John S.

    A secure, multiproject facility named the Integrated Technology Development Laboratories (ITDL) has been built. This paper gives some background information on how the ITDL came into existence, along with methods developed to provide for security and laboratory operations. Some details are discussed on the types of resources that are shared between projects, the software design, the hardware design, the power and ground, the communications system, and the configuration management needed to support secure, rapid configuration changes. The facility organization and logistics are also outlined.

  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. 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.

  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, 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.

  12. 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 third 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; integrated topping cycle/proof-of-concept current controls project; oxygen system storage upgrade; iron core magnet thermal protection system 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.

  13. 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.

  14. 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)

  15. Los Alamos Plutonium Facility implementation support project report

    SciTech Connect

    Thomas, C.C. Jr.; Ford, W.; Hsue, S.T.; Marshall, R.S.

    1982-05-01

    During FY 1981 the TA-55 Implementation Support Project provided assistance to the Los Alamos Plutonium Facility in materials accounting and control, including testing and evaluation of a solution mass measurement system, development and testing of a low-level plutonium assay system, holdup measurements, instrument design, and advice and consultation following the observation of semiannual inventories. This report describes the program envisioned for FY 1982, including demonstration of the solution mass measurement system and the associated calibration system, extension of the low-level plutonium assay system to solutions with americium/plutonium ratios of 10: to 20:1, and development and demonstration of a method to calibrate and routinely verify the plutonium oxalate assay instrument performance. The FY 1982 program is subject to changes based on TA-55 reevaluation of facility needs.

  16. 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

  17. 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.

  18. 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.

  19. 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.

  20. ALARA considerations for the whole body neutron irradiation facility source removal project at Brookhaven National Laboratory.

    PubMed

    Sullivan, Patrick T

    2006-02-01

    This paper describes the activities that were involved with the safe removal of fourteen PuBe sources from the Brookhaven National Laboratory (BNL) Whole Body Neutron Irradiation Facility (WBNIF). As part of a Department of Energy and BNL effort to reduce the radiological inventory, the WBNIF was identified as having no future use. In order to deactivate the facility and eliminate the need for nuclear safety management and long-term surveillance, it was decided to remove the neutron sources and dismantle the facility. In addition, the sources did not have DOT Special Form documentation so they would need to be encapsulated once removed for offsite storage or disposal. The planning and the administrative as well as engineering controls put in place enabled personnel to safely remove and encapsulate the sources while keeping exposure as low as reasonably achievable (ALARA). PMID:16404183

  1. 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.

  2. 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.

  3. 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).

  4. 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.

  5. 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.

  6. 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.

  7. Project implementation plan: ASTD remote deployment

    SciTech Connect

    CRASS, D.W.

    1999-08-18

    This Project Implementation Plan (PIP) shall be the controlling document for the Accelerated Site Technology Deployment (ASTD) supported project to procure and qualify a remote/robotic work platform for large hot cell deactivation in the 324 Building B-Cell. This plan will be integrated into the 324/327 Buildings Stabilization/Deactivation Project, Project Management Plan, (HNF-IP-1289, Rev. 1) and shall comply with the base requirements established in that document. This PIP establishes the baseline and defines the scope, schedule, budget, organizational responsibilities, reporting requirements, deliverables, and end points for the implementation of new technology into B-Cell. This shall include procurement, safety, quality assurance, training, documentation, record management, and facility modifications applicable to this project. Specifically this plan controls and executes the procurement and acceptance, qualification, and turnover of a remote/robotic work platform for 324 Building B-Cell. This includes the development of functional parameters, performance requirements, evaluation criteria, procurement specifications, acceptance and qualification test procedures, training requirements, and turnover responsibilities. The 324/237 Buildings Stabilization/Deactivation Project is currently in its second year of a nine-year project to complete deactivation and closure of the facility for long-term surveillance and maintenance. A major obstacles for the project is the inability to effectively perform deactivation tasks within high radioactively contaminated hot cells. The current strategies utilize inefficient and resource intensive technologies that significantly impact the cost and schedule for stabilization and deactivation. The ASTD Remote Deployment Project shall identify, procure, and turnover, to the B-Cell project, a remote/robot work platform to improve B-Cell cleanup productivity and enhance worker safety and health.

  8. 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…

  9. 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.

  10. 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.

  11. 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.

  12. Liquid metal reactor deactivation as applied to the experimental breeder reactor - II.

    SciTech Connect

    Earle, O. K.; Michelbacher, J. A.; Pfannenstiel, D. F.; Wells, P. B.

    1999-05-28

    The Experimental Breeder Reactor-II (EBR-II) at Argonne National Laboratory-West (ANL-W) was shutdown in September, 1994. This sodium cooled reactor had been in service since 1964, and by the US Department of Energy (DOE) mandate, was to be placed in an industrially and radiologically safe condition for ultimate decommissioning. The deactivation of a liquid metal reactor presents unique concerns. The first major task associated with the project was the removal of all fueled assemblies. In addition, sodium must be drained from systems and processed for ultimate disposal. Residual quantities of sodium remaining in systems must be deactivated or inerted to preclude future hazards associated with pyrophoricity and generation of potentially explosive hydrogen gas. A Sodium Process Facility (SPF) was designed and constructed to react the elemental sodium from the EBR-II primary and secondary systems to sodium hydroxide for disposal. This facility has a design capacity to allow the reaction of the complete inventory of sodium at ANL-W in less than two years. Additional quantities of sodium from the Fermi-1 reactor are also being treated at the SPF.

  13. 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.

  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. Controlled-deactivation cannabinergic ligands.

    PubMed

    Sharma, Rishi; Nikas, Spyros P; Paronis, Carol A; Wood, Jodianne T; Halikhedkar, Aneetha; Guo, Jason Jianxin; Thakur, Ganesh A; Kulkarni, Shashank; Benchama, Othman; Raghav, Jimit Girish; Gifford, Roger S; Järbe, Torbjörn U C; Bergman, Jack; Makriyannis, Alexandros

    2013-12-27

    We report an approach for obtaining novel cannabinoid analogues with controllable deactivation and improved druggability. Our design involves the incorporation of a metabolically labile ester group at the 2'-position on a series of (-)-Δ(8)-THC analogues. We have sought to introduce benzylic substituents α to the ester group which affect the half-lives of deactivation through enzymatic activity while enhancing the affinities and efficacies of individual ligands for the CB1 and CB2 receptors. The 1'-(S)-methyl, 1'-gem-dimethyl, and 1'-cyclobutyl analogues exhibit remarkably high affinities for both CB receptors. The novel ligands are susceptible to enzymatic hydrolysis by plasma esterases in a controllable manner, while their metabolites are inactive at the CB receptors. In further in vitro and in vivo experiments key analogues were shown to be potent CB1 receptor agonists and to exhibit CB1-mediated hypothermic and analgesic effects.

  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. Expedited technology demonstration project (Revised mixed waste management facility project) Project baseline revision 4.0 and FY98 plan

    SciTech Connect

    Adamson, M. G.

    1997-10-01

    The re-baseline of the Expedited Technology Demonstration Project (Revised Mixed Waste Facility Project) is designated as Project Baseline Revision 4.0. The last approved baseline was identified as Project Baseline Revision 3.0 and was issued in October 1996. Project Baseline Revision 4.0 does not depart from the formal DOE guidance followed by, and contained in, Revision 3.0. This revised baseline document describes the MSO and Final Forms testing activities that will occur during FY98, the final year of the ETD Project. The cost estimate for work during FY98 continues to be $2.OM as published in Revision 3.0. However, the funds will be all CENRTC rather than the OPEX/CENTRC split previously anticipated. LLNL has waived overhead charges on ETD Project CENRTC funds since the beginning of project activities. By requesting the $2.OM as all CENTRC a more aggressive approach to staffing and testing can be taken. Due to a cost under- run condition during FY97 procurements were made and work was accomplished, with the knowledge of DOE, in the Feed Preparation and Final Forms areas that were not in the scope of Revision 3.0. Feed preparation activities for FY98 have been expanded to include the drum opening station/enclosure previously deleted.

  19. 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.

  20. 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.

  1. Yucca Mountain Site Characterization Project exploratory studies facilities construction status

    SciTech Connect

    Allan, J.N.; Leonard, T.M.

    1993-12-31

    This paper discusses the progress to date on the construction planning and development of the Yucca Mountain Site Characterization Project (YMP) Exploratory Studies Facilities (ESF). The purpose of the ESF is to determine early site suitability and to characterize the subsurface of the Yucca Mountain site to assess its suitability for a potential high level nuclear waste repository. The present ESF configuration concept is for two main ramps to be excavated by tunnel boring machines (TBM) from the surface to the Topopah Spring Member of the Paintbrush Tuff Formation. From the main ramps, slightly above Topopah Spring level, supplemental ramps will be penetrated to the Calico Hills formation below the potential repository. There will be exploratory development drifts driven on both levels with the Main Test Area being located on the Topopah Spring level, which is the level of the proposed repository. The Calico Hills formation lies below the Topopah Spring member and is expected to provide the main geo-hydrologic barrier between the potential repository and the underlying saturated zones in the Crater Flat Tuff.

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. Endotoxin Deactivation by Transient Acidification

    PubMed Central

    Ribeiro, Melina M.; Xu, Xiumin; Klein, Dagmar; Kenyon, Norma S; Ricordi, Camillo; Felipe, Maria Sueli S.; Pastori, Ricardo L.

    2015-01-01

    Recombinant proteins are an important tool for research and therapeutic applications. Therapeutic proteins have been delivered to several cell types and tissues and might be used to improve the outcome of the cell transplantation. Recombinant proteins are propagated in bacteria, which will contaminate them with the lypopolysacharide-endotoxin found in the outer bacterial membrane. Endotoxin could interfere with in vitro biological assays and is the major pathological factor, which must be removed or inactivated before in vivo administration. Here we describe a one-step protocol in which the endotoxin activity on recombinant proteins is remarkably reduced by transient exposure to acidic conditions. Maximum endotoxin deactivation occurs at acidic pH below their respective isoelectric point (pI). This method does not require additional protein purification or separation of the protein from the endotoxin fraction. The endotoxin level was measured both in vitro and in vivo. For in vitro assessment we have utilized Limulus Amebocyte Lysate method for in vivo the pyrogenic test. We have tested the above-mentioned method with 5 different recombinant proteins including a monoclonal antibody clone 5c8 against CD154 produced by hybridomas. More than 99% of endotoxin was deactivated in all of the proteins, the recovery of the protein after deactivation varied between maximum 72.9 and minimum 46.8%. The anti CD154 clone 5c8 activity remained unchanged as verified by the measurement of binding capability to activated lymphocytes. Furthermore, the effectiveness of this method was not significantly altered by urea, commonly used in protein purification. This procedure provides a simple and cost-efficient way to reduce the endotoxin activity in antibodies and recombinant proteins. PMID:20412635

  7. 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.

  8. Catalyst deactivation in residue hydrocracking

    SciTech Connect

    Oballa, M.C.; Wong, C.; Krzywicki, A.

    1994-12-31

    The existence of a computer-controlled bench scale hydrocracking units at the authors site has made cheaper the non-stop running of experiments for long periods of time. It was, therefore possible to show, at minimal costs, when three hydrocracking catalysts in service reach their maximum lifetime. Different parameters which are helpful for catalyst life and activity predictions were calculated, e.g., relative catalyst age and the effectiveness factor. Experimental results compared well with model, giving them the minimum and maximum catalyst lifetime, as well as the deactivation profile with regard to sulfur and metals removal. Reaction rate constants for demetallization and desulfurization were also determined. Six commercial catalysts were evaluated at short term runs and the three most active were used for long term runs. Out of three catalysts tested for deactivation at long term runs, it was possible to choose one whose useful life was higher than the others. All runs were carried out in a Robinson-Mahoney continuous flow stirred tank reactor, using 50/50 volumetric mixture of Cold Lake/Lloydminster atmospheric residue and NiMo/Al{sub 2}O{sub 3} catalyst.

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  16. 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.

  17. 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.

  18. 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

  19. 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.

  20. 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.

  1. 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.

  2. 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.

  3. NETL - Fuel Reforming Facilities

    ScienceCinema

    None

    2016-07-12

    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.

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF INTERIOR Bureau of Reclamation Cancellation of the South Valley Facilities Expansion Project-- Clark County,...

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  16. 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.

  17. 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.

  18. Upgrading auxiliary facility outleakage and combustion detection. Final project report

    SciTech Connect

    Sandman, R.R.

    1984-12-20

    A new GAT preventive maintenance method, IMG-104, patterned after a similar successful procedure in use at the Oak Ridge Gaseous Diffusion Plant (ORGDP), was issued 2/3/84 to improve the performance of the specially modified Pyrotronics HF/F/sub 2/ detectors used in the X-342-A HF vaporizer bay and X-344-C HF storage facilities. Detector thermal protection was added/improved to increase cold-weather sensitivity and reduce moisture absorption by the detectors' dibutylamine reagent. Other moisture problems previously experienced by the X-342-A feed vaporization facility UF/sub 6/ outleakage/combustion unmodified detectors were eliminated following replacement of the twelve ''open'' steam chests with two totally-enclosed autoclaves, and installation of a new out-leakage/combustion detection system. Practical alternate methods of detecting UF/sub 6/ outleakage and combustion by-products are discussed, as is substitution of the reagent used in the HF/F/sub 2/ detectors; however, no changes were recommended.

  19. 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.

  20. 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.

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. Deuteron injector for Peking University Neutron Imaging Facility project

    SciTech Connect

    Ren, H. T.; Chen, J. E.; Peng, S. X.; Lu, P. N.; Zhou, Q. F.; Yuan, Z. X.; Zhao, J.; Zhang, M.; Song, Z. Z.; Yu, J. X.; Guo, Z. Y.

    2012-02-15

    The deuteron injector developed for the PKUNIFTY (Peking University Neutron Imaging Facility) has been installed and commissioned at Peking University (PKU). The injector system must transfer 50 keV 50 mA of D{sup +} ion beam to the entrance of the 2 MeV radio frequency quadrupole (RFQ) with 10% duty factor (1 ms, 100 Hz). A compact 2.45 GHz permanent magnet electron cyclotron resonance (PMECR) ion source and a 1.36 m long low energy beam transport (LEBT) line using two solenoids was developed as the deuteron injector. A {phi}5 mm four-quadrant diaphragm was used to simulate the entrance of RFQ electrodes. The beam parameters are measured after this core with an emittance measurement unit (EMU) and a bending magnet for ion fraction analysis at the end of injector. During the commissioning, 77 mA of total deuteron beam was extracted from PMECR and 56 mA of pure D{sup +} beam that passed through the {phi}5 mm four-quadrant diaphragm was obtained at the position of RFQ entrance with the measured normalized rms emittance 0.12-0.16{pi} mm mrad. Ion species analysis results show that the deuteron fraction is as high as 99.5%. All of the parameters satisfy PKUNIFTY's requirements. In this paper, we will describe the deuteron injector design and report the commissioning results as well as the initial operation.

  6. Deuteron injector for Peking University Neutron Imaging Facility project.

    PubMed

    Ren, H T; Peng, S X; Lu, P N; Zhou, Q F; Yuan, Z X; Zhao, J; Zhang, M; Song, Z Z; Yu, J X; Guo, Z Y; Chen, J E

    2012-02-01

    The deuteron injector developed for the PKUNIFTY (Peking University Neutron Imaging Facility) has been installed and commissioned at Peking University (PKU). The injector system must transfer 50 keV 50 mA of D(+) ion beam to the entrance of the 2 MeV radio frequency quadrupole (RFQ) with 10% duty factor (1 ms, 100 Hz). A compact 2.45 GHz permanent magnet electron cyclotron resonance (PMECR) ion source and a 1.36 m long low energy beam transport (LEBT) line using two solenoids was developed as the deuteron injector. A φ5 mm four-quadrant diaphragm was used to simulate the entrance of RFQ electrodes. The beam parameters are measured after this core with an emittance measurement unit (EMU) and a bending magnet for ion fraction analysis at the end of injector. During the commissioning, 77 mA of total deuteron beam was extracted from PMECR and 56 mA of pure D(+) beam that passed through the φ5 mm four-quadrant diaphragm was obtained at the position of RFQ entrance with the measured normalized rms emittance 0.12-0.16π mm mrad. Ion species analysis results show that the deuteron fraction is as high as 99.5%. All of the parameters satisfy PKUNIFTY's requirements. In this paper, we will describe the deuteron injector design and report the commissioning results as well as the initial operation.

  7. Part 2: Evaluation and outcomes of an evidence-based facility design project.

    PubMed

    Krugman, Mary; Sanders, Carolyn; Kinney, Lisa J

    2015-02-01

    Based on the work of a TCAB facility design team at an academic hospital (part 1), an evaluation project was implemented to measure RN work environment perceptions, work activity sampling, and steps walked on 6 units moving into a new acute care pavilion. Pre and post data reported significant nurse satisfaction post move with the new work environment. Workflow sampling data did not reflect significant changes; the pedometer device used to measure nurse steps proved unreliable. Project evaluation data are reported.

  8. 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.

  9. 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.

  10. PROJECT EXPERIENCE REPORT DEMOLITION OF HANFORDS 233-S PLUTONIUM CONCENTRATION FACILITY

    SciTech Connect

    BERLIN, G.T.

    2004-06-25

    This report provides a summary of the preparation, operations, innovative work practices, and lessons learned associated with demolition of the 2334 Plutonium Concentration Facility. This project represented the first open-air demolition of a highly-contaminated plutonium facility at the Hanford Site. This project may also represent the first plutonium facility in the US. Department of Energy (DOE) complex to have been demolished without first decontaminating surfaces to near ''free release'' standards. Demolition of plutonium contaminated structures, if not properly managed, can subject cleanup personnel and the environment to significant risk. However, with proper sequencing and innovative use of commercially available equipment, materials, and services, this project demonstrated that a plutonium processing facility can be demolished while avoiding the need to perform extensive decontamination or to construct large enclosures. This project utilized an excavator with concrete shears, diamond circular saws, water misting and fogging equipment, commercially available fixatives and dust suppressants, conventional mobile crane and rigging services, and near real-time modeling of meteorological and radiological conditions. Following a significant amount of preparation, actual demolition of the 2333 Facility began in October 2003 and was completed in late April 2004. The knowledge and experience gained on this project are important to the Hanford Site as additional plutonium processing facilities are scheduled for demolition in the near future. Other sites throughout the DOE Complex may also be faced with similar challenges. Numerous innovations and effective work practices were implemented on this project. Accordingly, a series of ''Lessons Learned and Innovative Practices Fact Sheets'' were developed and are included as an appendix to this report. This collection of fact sheets is not intended to capture every innovative work practice and lesson learned, but rather to

  11. PROJECT EXPERIENCE REPORT DEMOLITION OF HANFORDS 233-S PLUTONIUM CONCENTRATION FACILITY

    SciTech Connect

    BERLIN, G.T.; ORGILL, T.K.

    2004-07-14

    This report provides a summary of the preparation, operations, innovative work practices, and lessons learned associated with demolition of the 2334 Plutonium Concentration Facility. This project represented the first open-air demolition of a highly-contaminated plutonium facility at the Hanford Site. This project may also represent the first plutonium facility in the US. Department of Energy (DOE) complex to have been demolished without first decontaminating surfaces to near ''free release'' standards. Demolition of plutonium contaminated structures, if not properly managed, can subject cleanup personnel and the environment to significant risk. However, with proper sequencing and innovative use of commercially available equipment, materials, and services, this project demonstrated that a plutonium processing facility can be demolished while avoiding the need to perform extensive decontamination or to construct large enclosures. This project utilized an excavator with concrete shears, diamond circular saws, water misting and fogging equipment, commercially available fixatives and dust suppressants, conventional mobile crane and rigging services, and near real-time modeling of meteorological and radiological conditions. Following a significant amount of preparation, actual demolition of the 233-S Facility began in October 2003 and was completed in late April 2004. The knowledge and experience gained on this project are important to the Hanford Site as additional plutonium processing facilities are scheduled for demolition in the near future. Other sites throughout the DOE Complex may also be faced with similar challenges. Numerous innovations and effective work practices were implemented on this project. Accordingly, a series of ''Lessons Learned and Innovative Practices Fact Sheets'' were developed and are included as an appendix to this report. This collection of fact sheets is not intended to capture every innovative work practice and lesson learned, but rather

  12. 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...

  13. 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...

  14. 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...

  15. 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...

  16. 75 FR 39926 - Deer Creek Station Energy Facility Project (DOE/EIS-0415)

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-07-13

    ... a new 300-megawatt (MW) natural gas-fired combined-cycle generation facility in Brookings County... line, two water wells, a 1.25-mile water supply line, and 1 mile of local road improvements. Western... Iowa. Western published a Notice of Intent to prepare an EIS for the project on February 6, 2009 (74...

  17. The Delinquent in a State Residential Facility for the Mentally Retarded Project CAMIO, Volume 6.

    ERIC Educational Resources Information Center

    Haskins, Jimmy R.; Friel, Charles M.

    Evaluated were 430 new juvenile and adult admissions to a state residential facility for the mentally retarded (MR). The study was part of Project CAMIO (Correctional Administration and the Mentally Incompetent Offender), a Texas effort to determine the incidence of criminal incarceration of the MR and to identify laws, procedures, and practices…

  18. 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)

  19. 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.

  20. 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.

  1. 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.

  2. 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.

  3. 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)

  4. 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.

  5. 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

  6. 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.

  7. 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.

  8. 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

  9. 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.…

  10. 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...

  11. 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...

  12. 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...

  13. 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...

  14. 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

    ... Bureau of Reclamation Cle Elum Dam Fish Passage Facilities and Fish Reintroduction Project; Kittitas... 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...

  15. 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.

  16. WICHE Management Information Systems Program. Higher Education Facilities Planning and Management Manuals Project. (SAM-Space Analysis Manuals Project) Project Description.

    ERIC Educational Resources Information Center

    Western Interstate Commission for Higher Education, Boulder, CO.

    This report describes the basic objectives, assumptions, orientation and development of the Space Analysis Manuals Project. The main objective is to write and distribute a series of annuals describing methods and procedures for use by college and university personnel in planning and managing college and university facilities. One of the basic…

  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. US Department of Energy Grand Junction Projects Office Remedial Action Project, final report of the decontamination and decommissioning of Building 36 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. Building 36 was found to be radiologically contaminated and was demolished in 1996. The soil beneath the building was remediated in accordance with identified standards and 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.

  19. 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).

  20. 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.

  1. Space Station Furnace Facility preliminary Project Implementation Plan (PIP). Volume 2, appendix 2

    NASA Astrophysics Data System (ADS)

    Perkey, John K.

    1992-05-01

    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.

  2. 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.

  3. 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).

  4. U.S. Environmental Protection Agency Clear Air Act notice of construction for the spent nuclear fuel project - Cold Vaccum Drying Facility, project W-441

    SciTech Connect

    Turnbaugh, J.E.

    1996-11-25

    This document provides information regarding the source and the estimated quantity of potential airborne radionuclide emissions resulting from the operation of the Cold Vacuum Drying (CVD) Facility. The construction of the CVD Facility is scheduled to commence on or about December 1996, and will be completed when the process begins operation. This document serves as a Notice of Construction (NOC) pursuant to the requirements of 40 Code of Federal Regulations (CFR) 61 for the CVD Facility. About 80 percent of the U.S. Department of Energy`s spent nuclear fuel (SNF) inventory is stored under water in the Hanford Site K Basins. Spent nuclear fuel in the K West Basin is contained in closed canisters, while the SNF in the K East Basin is in open canisters, which allow release of corrosion products to the K East Basin water. Storage of the current inventory in the K Basins was originally intended to be on an as-needed basis to sustain operation of the N Reactor while the Plutonium-Uranium Extraction (PUREX) Plant was refurbished and restarted. The decision in December 1992 to deactivate the PURF-X Plant left approximately 2,100 MT (2,300 tons) of uranium as part of the N Reactor SNF in the K Basins with no means for near-term removal and processing. The CVD Facility will be constructed in the 100 Area northwest of the 190 K West Building, which is in close proximity to the K East and K West Basins (Figures 1 and 08572). The CVD Facility will consist of five processing bays, with four of the bays fully equipped with processing equipment and the fifth bay configured as an open spare bay. The CVD Facility will have a support area consisting of a control room, change rooms, and other functions required to support operations.

  5. 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

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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

  12. 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.

  13. Final report of the HFIR (High Flux Isotope Reactor) irradiation facilities improvement project

    SciTech Connect

    Montgomery, B.H.; Thoms, K.R.; West, C.D.

    1987-09-01

    The High-Flux Isotope Reactor (HFIR) has outstanding neutronics characteristics for materials irradiation, but some relatively minor aspects of its mechanical design severely limited its usefulness for that purpose. In particular, though the flux trap region in the center of the annular fuel elements has a very high neutron flux, it had no provision for instrumentation access to irradiation capsules. The irradiation positions in the beryllium reflector outside the fuel elements also have a high flux; however, although instrumented, they were too small and too few to replace the facilities of a materials testing reactor. To address these drawbacks, the HFIR Irradiation Facilities Improvement Project consisted of modifications to the reactor vessel cover, internal structures, and reflector. Two instrumented facilities were provided in the flux trap region, and the number of materials irradiation positions in the removable beryllium (RB) was increased from four to eight, each with almost twice the available experimental space of the previous ones. The instrumented target facilities were completed in August 1986, and the RB facilities were completed in June 1987.

  14. 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

  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. 49 CFR 192.727 - Abandonment or deactivation of facilities.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... TRANSPORTATION OF NATURAL AND OTHER GAS BY PIPELINE: MINIMUM FEDERAL SAFETY STANDARDS Maintenance § 192.727... disconnected from all sources and supplies of gas; purged of gas; in the case of offshore pipelines, filled... the volume of gas is so small that there is no potential hazard. (c) Except for service lines,...

  18. 49 CFR 195.59 - Abandonment or deactivation of facilities.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... System (NPMS) in accordance with the NPMS “Standards for Pipeline and Liquefied Natural Gas Operator... in accordance with applicable laws. Refer to the NPMS Standards for details in preparing your data... abandoned in accordance with all applicable laws. (b)...

  19. 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.

  20. Excel Automatic Locking Scaffold. Deactivation and Decommissioning Focus Area. OST Reference #2320

    SciTech Connect

    None, None

    1999-09-01

    The United States Department of Energy (DOE) continually seeks safer and more cost-effective technologies for 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 sponsors large-scale demonstration and deployment projects (LSDDPs). At these LSDDPs, developers and vendors of improved or innovative technologies showcase products that are potentially beneficial to the 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 need statements defining specific needs or problems where improved technologies could be incorporated into ongoing D&D tasks. Although not addressed explicitly, the use of scaffolds is needed in several of the listed needs, including characterization, demolition, and asbestos abatement. In these areas, scaffold towers are used to access areas that are not accessible using mechanical methods such as manlifts or mechanical platforms. In addition, the work requires more mobility than what can be achieved using ladders. Because of the wide use of scaffold on D&D projects, a need exists for a safer to use, faster to set up, and overall cheaper scaffold system. This demonstration investigated the feasibility of using the Excel Automatic Locking Scaffold (innovative technology) to access areas where tube and clamp scaffold (baseline) is currently being used on D&D activities. Benefits expected from using the innovative technology include: Decreased exposure to radiation, chemical, and/or physical hazards during scaffold erection and dismantlement; Increased safety; Easier use; Shorten D&D Schedule; Reduced cost of operation; Excel Scaffold is compatible with tube and clamp scaffold. This report

  1. 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.

  2. Projects of Nuclotron modernization and Nuclotron-based ion collider facility (NICA) at JINR

    NASA Astrophysics Data System (ADS)

    Lednicky, R.

    2008-09-01

    One of the basic facilities at the Joint Institute for Nuclear Research (JINR) in Dubna is the 6 A GeV Nuclotron, which has replaced the old weak focusing 10-GeV proton accelerator Synchrophasotron. The first relativistic nuclear beams with the energy of 4.2 A GeV were obtained at the Synchrophasotron in 1971. Since that time, relativistic nuclear physics has been one of the main directions of the JINR research program. In the coming years, the new JINR flagship program assumes the experimental study of hot and dense strongly interacting QCD matter at the new JINR facility. This goal is proposed to be reached by (i) development of the existing Nuclotron accelerator facility as a basis for generation of intense beams over atomic mass range from protons to uranium and light polarized ions, (ii) design and construction of the Nuclotron-based heavy Ion Collider fAcility (NICA) with the maximum nucleon-nucleon center-of-mass collision energy of √ s NN = 9 GeV and averaged luminosity 1027 cm-2 s-1, and (iii) design and construction of the Multipurpose Particle Detector (MPD) at intersecting beams. Realization of the project will lead to unique conditions for research activity of the world community. The NICA energy region is of major interest because the highest nuclear (baryonic) density under laboratory conditions can be reached there. Generation of intense polarized light nuclear beams aimed at investigation of polarization phenomena at the Nuclotron is foreseen.

  3. 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.

  4. 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... How does the Postal Service provide states an opportunity to comment on proposed facility...

  5. 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... How does the Postal Service provide states an opportunity to comment on proposed facility...

  6. 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... How does the Postal Service provide states an opportunity to comment on proposed facility...

  7. 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... How does the Postal Service provide states an opportunity to comment on proposed facility...

  8. 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.

  9. 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.

  10. 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.

  11. Lessons Learned from the On-Site Disposal Facility at Fernald Closure Project

    SciTech Connect

    Kumthekar, U.A.; Chiou, J.D.

    2006-07-01

    The On-Site Disposal Facility (OSDF) at the U.S. Department of Energy's (DOE) Fernald Closure Project near Cincinnati, Ohio is an engineered above-grade waste disposal facility being constructed to permanently store low level radioactive waste (LLRW) and treated mixed LLRW generated during Decommissioning and Demolition (D and D) and soil remediation performed in order to achieve the final land use goal at the site. The OSDF is engineered to store 2.93 million cubic yards of waste derived from the remediation activities. The OSDF is intended to isolate its LLRW from the environment for at least 200 years and for up to 1,000 years to the extent practicable and achievable. Construction of the OSDF started in 1997 and waste placement activities will complete by the middle of April 2006 with the final cover (cap) placement over the last open cell by the end of Spring 2006. An on-site disposal alternative is considered critical to the success of many large-scale DOE remediation projects throughout the United States. However, for various reasons this cost effective alternative is not readily available in many cases. Over the last ten years Fluor Fernald Inc. has cumulated many valuable lessons learned through the complex engineering, construction, operation, and closure processes of the OSDF. Also in the last several years representatives from other DOE sites, State agencies, as well as foreign government agencies have visited the Fernald site to look for proven experiences and practices, which may be adapted for their sites. This paper present a summary of the major issues and lessons leaned at the Fernald site related to engineering, construction, operation, and closure processes for the disposal of remediation waste. The purpose of this paper is to share lessons learned and to benefit other projects considering or operating similar on-site disposal facilities from our successful experiences. (authors)

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  16. 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.

  17. Planning for closure and deactivation of the EBR-II complex

    SciTech Connect

    Michelbacher, J.A.; Henslee, S.P.; Poland, H.F.; Wells, P.B.

    1997-07-01

    In January 1994, DOE terminated the Integral Fast Reactor (IFR) Program. Argonne National Laboratory-West (ANL-W) prepared a detailed plan to put Experimental Breeder Reactor-II (EBR-II) in a safe condition, including removal of irradiated fueled subassemblies from the plant, transfer of subassemblies, and removal and stabilization of primary and secondary sodium liquid heat transfer metal. The goal of deactivation is to stabilize the EBR-II complex until decontamination and decommissioning (D&D) is implemented, thereby minimizing maintenance and surveillance. Deactivation of a sodium cooled reactor presents unique concerns. Residual sodium in the primary and secondary systems must be either reacted or inerted to preclude concerns with explosive sodium-air reactions. Also, residual sodium on components will effectively solder these items in place, making removal unfeasible. Several special cases reside in the primary system, including primary cold traps, a cesium trap, a cover gas condenser, and systems containing sodium-potassium alloy. The sodium or sodium-potassium alloy in these components must be reacted in place or the components removed. The Sodium Components Maintenance Shop at ANL-W provides the capability for washing primary components, removing residual quantities of sodium while providing some decontamination capacity. Considerations need to be given to component removal necessary for providing access to primary tank internals for D&D activities, removal of hazardous materials, and removal of stored energy sources. ANL-W`s plan for the deactivation of EBR-II addresses these issues, providing for an industrially and radiologically safe complex, requiring minimal surveillance during the interim period between deactivation and D&D. Throughout the deactivation and closure of the EBR-II complex, federal environmental concerns will be addressed, including obtaining the proper permits for facility condition and waste processing and disposal. 2 figs.

  18. 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.

  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. 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

  1. 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

  2. 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.

  3. 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.

  4. 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

  5. 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.

  6. 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...

  7. 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...

  8. 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...

  9. 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...

  10. 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...

  11. 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

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  16. 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).

  17. 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.

  18. 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).

  19. 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

  20. 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}

  1. 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

  2. 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.

  3. 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.

  4. 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.

  5. Small-scale hydroelectric demonstration project: Reactivation of the Elk Rapids Hydroelectric Facility: Final operation and maintenance report

    SciTech Connect

    Miller, R.G.

    1987-03-01

    Information related to the reactivation of the Elk River Hydroelectric Power facility is reported. This report includes a history of the power plant, pertinent cost data, emergency action plans, inspections and testing, warranty work, operating problems, project data, monthly production data, and monthly operating and maintenance costs. 15 figs., 3 tabs.

  6. 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...

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

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 7 Agriculture 14 2014-01-01 2014-01-01 false 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,...

  8. 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

    ... 7 Agriculture 14 2013-01-01 2013-01-01 false 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,...

  9. Fitness-driven deactivation in network evolution

    NASA Astrophysics Data System (ADS)

    Xu, Xin-Jian; Peng, Xiao-Long; Small, Michael; Fu, Xin-Chu

    2010-12-01

    Individual nodes in evolving real-world networks typically experience growth and decay—that is, the popularity and influence of individuals peaks and then fades. In this paper, we study this phenomenon via an intrinsic nodal fitness function and an intuitive ageing mechanism. Each node of the network is endowed with a fitness which represents its activity. All the nodes have two discrete stages: active and inactive. The evolution of the network combines the addition of new active nodes randomly connected to existing active ones and the deactivation of old active nodes with a possibility inversely proportional to their fitnesses. We obtain a structured exponential network when the fitness distribution of the individuals is homogeneous and a structured scale-free network with heterogeneous fitness distributions. Furthermore, we recover two universal scaling laws of the clustering coefficient for both cases, C(k) ~ k - 1 and C ~ n - 1, where k and n refer to the node degree and the number of active individuals, respectively. These results offer a new simple description of the growth and ageing of networks where intrinsic features of individual nodes drive their popularity, and hence degree.

  10. 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.

  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. Automated Activation and Deactivation of a System Under Test

    NASA Technical Reports Server (NTRS)

    Poff, Mark A.

    2006-01-01

    The MPLM Automated Activation/Deactivation application (MPLM means Multi-Purpose Logistic Module) was created with a three-fold purpose in mind: 1. To reduce the possibility of human error in issuing commands to, or interpreting telemetry from, the MPLM power, computer, and environmental control systems; 2. To reduce the amount of test time required for the repetitive activation/deactivation processes; and 3. To reduce the number of on-console personnel required for activation/ deactivation. All of these have been demonstrated with the release of the software. While some degree of automated end-item commanding had previously been performed for space-station hardware in the test environment, none approached the functionality and flexibility of this application. For MPLM activation, it provides mouse-click selection of the hardware complement to be activated, activates the desired hardware and verifies proper feedbacks, and alerts the user when telemetry indicates an error condition or manual intervention is required. For MPLM deactivation, the product senses which end items are active and deactivates them in the proper sequence. For historical purposes, an on-line log is maintained of commands issued and telemetry points monitored. The benefits of the MPLM Automated Activation/ Deactivation application were demonstrated with its first use in December 2002, when it flawlessly performed MPLM activation in 8 minutes (versus as much as 2.4 hours for previous manual activations), and performed MPLM deactivation in 3 minutes (versus 66 minutes for previous manual deactivations). The number of test team members required has dropped from eight to four, and in actuality the software can be operated by a sole (knowledgeable) system engineer.

  14. 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.

  15. 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.

  16. Catalyst deactivation in hydrotreating of residua: A review

    SciTech Connect

    Bartholomew, C.H.

    1994-12-31

    Hydrotreating of petroleum residua feedstocks involves three important reactions: hydrodesulfurization (HDS), hydrodenitrogenation (HDN), and hydrodemetallization (HDM) for removal of organically-bound sulfur, nitrogen, and metals respectively. Sulfided resid hydrotreating catalysts are deactivated over a period of months by coke, metals and nitrogen compounds. The deactivation process involves a combination of uniform poisoning, pore mouth poisoning and pore blockage by (i) decomposition of organometallic compounds and (ii) buildup of soft coke and its transformation over a period of time to hard, crystalline coke. These problems are minimized by careful selection of guard beds, reactor design, and catalyst design; moreover, it is possible to regenerate coked catalysts with an oxygen burn. An updated overview of the key aspects of residua hydrotreating deactivation, including coke formation chemistry, metals deposition chemistry, catalyst and reactor design, and the use of mathematical models to simulate the deactivation process may be timely. This review focuses on the deactivation of sulfided Mo, CoMo, and NiMo catalysts in hydrotreating of heavy residuum feedstocks. Coke formation, metals deposition, the roles of catalyst and reactor design in minimizing catalyst decline, and the application of modeling to design and prediction of deactivation rates are discussed in this review in the sections which follow. 42 refs., 16 figs., 2 tabs.

  17. 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.

  18. 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.

  19. Healy Clean Coal Project, Healy FCM testing at Niro Air Pollution Control Pilot Facility. Final report

    SciTech Connect

    Not Available

    1992-10-01

    In September, 1991, pilot testing was performed at the Niro Air Pollution Control Pilot Plant in Copenhagen, Denmark in support of the Healy Clean Coal Project (HCCP), which is part of the United States Department of Energy (DOE) Clean Coal Technology Ill Program. The HCCP is a proposed new coal fired power plant, located in Healy, Alaska. It consists of a TRW entrained combustion system, coupled with a limestone calciner, which operates in synergism with a Joy/Niro Spray Dryer Absorber (SDA) system equipped with a lime activation system that is designed to increase the utilization of the calcined product for sulfur capture in the SDA. The pilot tests, which were funded by the United States Department of Energy (DOE) and the Alaska Industrial Development and Export Authority (AIDEA), were conducted to investigate the characteristics of the TRW combustor/limestone calciner product, referred to as Flash Calcined Material (FCM) with respect to its ability to remove S0{sub 2 } in the Joy/Niro Activated Recycle SDA system. This report describes the pilot facility, the test objectives and methods, and the results of the tests.

  20. Healy Clean Coal Project, Healy FCM testing at Niro Air Pollution Control Pilot Facility

    SciTech Connect

    Not Available

    1992-10-01

    In September, 1991, pilot testing was performed at the Niro Air Pollution Control Pilot Plant in Copenhagen, Denmark in support of the Healy Clean Coal Project (HCCP), which is part of the United States Department of Energy (DOE) Clean Coal Technology Ill Program. The HCCP is a proposed new coal fired power plant, located in Healy, Alaska. It consists of a TRW entrained combustion system, coupled with a limestone calciner, which operates in synergism with a Joy/Niro Spray Dryer Absorber (SDA) system equipped with a lime activation system that is designed to increase the utilization of the calcined product for sulfur capture in the SDA. The pilot tests, which were funded by the United States Department of Energy (DOE) and the Alaska Industrial Development and Export Authority (AIDEA), were conducted to investigate the characteristics of the TRW combustor/limestone calciner product, referred to as Flash Calcined Material (FCM) with respect to its ability to remove S0[sub 2 ] in the Joy/Niro Activated Recycle SDA system. This report describes the pilot facility, the test objectives and methods, and the results of the tests.

  1. 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

  2. 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.

  3. 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

  4. 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.

  5. Selective inhibition of deactivated mitochondrial complex I by biguanides.

    PubMed

    Matsuzaki, Satoshi; Humphries, Kenneth M

    2015-03-24

    Biguanides are widely used antihyperglycemic agents for diabetes mellitus and prediabetes treatment. Complex I is the rate-limiting step of the mitochondrial electron transport chain (ETC), a major source of mitochondrial free radical production, and a known target of biguanides. Complex I has two reversible conformational states, active and de-active. The deactivated state is promoted in the absence of substrates but is rapidly and fully reversed to the active state in the presence of NADH. The objective of this study was to determine the relative sensitivity of active/de-active complex I to biguanide-mediated inhibition and resulting superoxide radical (O₂(•⁻)) production. Using isolated rat heart mitochondria, we show that deactivation of complex I sensitizes it to metformin and phenformin (4- and 3-fold, respectively), but not to other known complex I inhibitors, such as rotenone. Mitochondrial O₂(•⁻) production by deactivated complex I was measured fluorescently by NADH-dependent 2-hydroxyethidium formation at alkaline pH to impede reactivation. Superoxide production was 260.4% higher than in active complex I at pH 9.4. However, phenformin treatment of de-active complex I decreased O₂(•⁻) production by 14.9%, while rotenone increased production by 42.9%. Mitochondria isolated from rat hearts subjected to cardiac ischemia, a condition known to induce complex I deactivation, were sensitized to phenformin-mediated complex I inhibition. This supports the idea that the effects of biguanides are likely to be influenced by the complex I state in vivo. These results demonstrate that the complex I active and de-active states are a determinant in biguanide-mediated inhibition.

  6. 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

  7. 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.

  8. Position paper: Live load design criteria for Project W-236A Multi-Function Waste Tank Facility

    SciTech Connect

    Giller, R.A.

    1995-06-09

    The purpose of this paper is to discuss the live loads applied to the underground storage tanks of the Multi Function Waste Tank Facility, and to provide the basis for Project W-236A live load criteria. Project 236A provides encompasses building a Weather Enclosure over the two underground storage tanks at the 200-West area. According to the Material Handling Study, the Groves AT 1100 crane used within the Weather Enclosure will have a gross vehicle weight of 66.5 tons. Therefore, a 100-ton concentrated live load is being used for the planning of the construction of the Weather Enclosure.

  9. 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.

  10. Deactivation by carbon of iron catalysts for indirect liquefaction

    SciTech Connect

    Bartholomew, C H

    1991-02-14

    Progress is reported for a four-year fundamental investigation of carbon formation and its effects on the activity and selectivity of promoted iron catalysts for FT synthesis, the objectives of which were to (1) determine rates and mechanisms of carbon deactivation of unsupported Fe and Fe/K catalysts during CO hydrogenation and (2) model the global rates of deactivation at the surface of the catalyst for the same catalysts. A computer-automated reactor system to be used in the kinetic and deactivation studies was designed, constructed and tested. Kinetic data for CO hydrogenation on unsupported, unpromoted iron, 99% Fe/1% Al{sub 2}O{sub 3}, and K-promoted 99% Fe/1% Al{sub 2}O{sub 3} catalysts were obtained as functions of temperature, reactant particle pressures and time. The activity/selectivity and kinetic data are consistent with those previously reported for supported, unpromoted and promoted iron. Two kinds of deactivation were observed during FT synthesis on these samples: (1) loss of surface area after reduction of unsupported, unpromoted iron at 400{degree}C and (2) loss of activity with time due to carbon deposition, especially in the case of K-promoted 99% Fe/1% A1{sub 2}O{sub 3}. Deactivation rate data were obtained for CO hydrogenation on promoted Fe as a function of time, temperature, and H{sub 2}/CO ratio. 50 refs., 24 figs., 5 tabs.

  11. 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.

  12. Final report of the decontamination and decommission of Building 31 at the Grand Junction Projects Office Facility

    SciTech Connect

    Krabacher, J.E.

    1996-07-01

    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 domestic uranium procurement program funded by the U.S. Atomic Energy Commission. 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. Radiological contamination was identified in Building 31 and the building was demolished in 1992. 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 area was addressed in the summary final report of the remediation of the exterior areas of the GJPO facility. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.

  13. 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.

  14. Final report of the decontamination and decommissioning of Building 44 at the Grand Junction Projects Office Facility

    SciTech Connect

    Widdop, M.R.

    1996-07-01

    The U.S. Department of Energy (DOE) 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, is also the remedial action contractor. Building 44 was radiologically contaminated and the building was demolished in 1994. The soil area within the footprint of the building was not contaminated; it complies 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.

  15. 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.

  16. 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.

  17. 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

  18. 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.

  19. Self-deactivation of water vapor - Role of the dimer

    NASA Technical Reports Server (NTRS)

    Zuckerwar, A. J.

    1984-01-01

    A phenomenological multiple-relaxation theory of the deactivation rate constant for the nu-2 (1 - 0) bending mode of water vapor is presented which incorporates the role not only of the excited monomer but also of the bound molecular complex, in particular the dimer. The deactivation takes place by means of three parallel processes: (1) collisional deexcitation of the excited monomer, (2) a two-step reaction involving association and spontaneous redissociation of an H2O collision complex, and (3) spontaneous dissociation of the stably bound H2O dimer. Oxygen, but not nitrogen or argon, serves as an effective chaperon for the formation of the activated complex. This observation explains the impurity dependence of the self-deactivation rate constant of water vapor. Analysis of an ultrasonic absorption peak based on the third process yields values for the standard entropy and enthalpy of dissociation of the stably bound H2O dimer.

  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. Deactivation of singlet oxygen by single-wall carbon nanohorns

    NASA Astrophysics Data System (ADS)

    Yanagi, Kazuhiro; Okazaki, Toshiya; Miyata, Yasumitsu; Kataura, Hiromichi

    2006-11-01

    The deactivation rate constant of singlet oxygen 1O 2 by single-wall carbon nanohorns (SWNHs) was determined. The estimated rate constant by SWNHs, 8 × 10 4 L g -1 s -1, was significantly larger than the physical quenching rate constant by α-Tocopherol, 0.9 × 10 4 L g -1 s -1. The origin of this remarkable efficiency of SWNHs for 1O 2 deactivation is ascribed to the unique curvature of the graphitic tube in their horn shaped structure.

  2. Systems and methods for deactivating a matrix converter

    DOEpatents

    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.

  3. 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.

  4. 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.

  5. 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.

  6. Final report of the decontamination and decommissioning of Building 6 at the Grand Junction Projects Office Facility

    SciTech Connect

    Widdop, M.R.

    1996-07-01

    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 domestic uranium procurement program funded by the U.S. Atomic Energy Commission. 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, is also the remedial action contractor. Radiological contamination was identified in Building 6, and the building was demolished in 1992. 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.

  7. Final report of the decontamination and decommissioning of Building 1 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. Building 1 was found to be radiologically contaminated and was demolished in 1996. The soil beneath and adjacent to the building was remediated in accordance with identified standards and 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.

  8. Final report of the decontamination and decommissioning of Building 39 at the Grand Junction Projects Office Facility

    SciTech Connect

    Widdop, M.R.

    1996-07-01

    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, is also the remedial action contractor. The soil beneath Building 39 was radiologically contaminated and the building was demolished in 1992. 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.

  9. 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

  10. 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.

  11. 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.

  12. A Comprehensive Literature Review of Mode Deactivation Therapy

    ERIC Educational Resources Information Center

    Houston, Marsha Ann; Apsche, Jack A.; Bass, Christopher K.

    2007-01-01

    In this article literature published on Mode Deactivation Therapy (MDT) was reviewed in depth. Several studies were identified that used a common outcome measure of reduction of physical and sexual aggression, other risk related behaviors. Comparisons of MDT and, other standardized approaches typically used in treating aggression in juveniles,…

  13. 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…

  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. 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...

  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. 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.

  18. 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.

  19. 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).

  20. 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.

  1. 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.

  2. 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.

  3. 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

  4. 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.

  5. The SHIPTRAP project: A capture and storage facility at GSI for heavy radionuclides from SHIP

    NASA Astrophysics Data System (ADS)

    Dilling, J.; Ackermann, D.; Bernard, J.; Hessberger, F. P.; Hofmann, S.; Hornung, W.; Kluge, H. J.; Lamour, E.; Maier, M.; Mann, R.; Marx, G.; Moore, R. B.; Münzenberg, G.; Quint, W.; Rodriguez, D.; Schädel, M.; Schönfelder, J.; Sikler, G.; Toader, C.; Vermeeren, L.; Weber, C.; Bollen, G.; Engels, O.; Habs, D.; Thirolf, P.; Backe, H.; Dretzke, A.; Lauth, W.; Ludolphs, W.; Sewtz, M.

    2000-08-01

    SHIPTRAP is an ion trap facility which is being set up to deliver very clean and cool beams of singly-charged recoil ions produced at the SHIP velocity filter at GSI Darmstadt. SHIPTRAP consists of a gas cell for stopping and thermalizing high-energy recoil ions from SHIP, a rf ion guide for extraction of the ions from the gas cell, a linear rf trap for accumulation and bunching of the ions, and a Penning trap for isobaric purification. The physics programme of the SHIPTRAP facility comprises mass spectrometry, nuclear spectroscopy, laser spectroscopy and chemistry of transeinsteinium elements.

  6. 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.

  7. Deactivation kinetics of the transduction cascade of vision.

    PubMed Central

    Vuong, T M; Chabre, M

    1991-01-01

    The response of the retinal rod cell to a dim flash lasts less than a second. This phototransduction is mediated by a guanine nucleotide-binding (G) protein cascade in which rhodopsin is the receptor, transducin is the G-protein, and the cGMP-specific phosphodiesterase (PDE) is the effector. Photoexcited rhodopsin activates transducin which in turn activates PDE. For this underlying biochemistry to be kinetically compatible with the photoresponse, both transducin and PDE must be deactivated in subsecond times. We report here direct measurements of their deactivation kinetics. The rate of heat release when transducin and PDE hydrolyze, respectively, GTP and cGMP was measured using time-resolved microcalorimetry. With only GTP present, the heat pulse comes from the activation of transducin and its subsequent deactivation by endogenous GTP hydrolysis. The nonhydrolyzable analog guanine 5'-[gamma-thio]triphosphate was used to distinguish between these two processes: about 40% of the total heat is due to activation. From the time course of the deactivation heat, the active lifetime of transducin is less than 1 s at 22 degrees C. With both GTP and cGMP present, the highly amplified hydrolytic activity of the PDE is responsible for most of the heat produced; its rate of release is directly proportional to the amount of activated PDE. Measurements of this rate at low photoexcitation levels (e.g., 30 molecules of photoexcited rhodopsin per rod) provide much kinetic information about the cascade. Notably, deactivation of the PDE takes 0.6 s (at 23 degrees C) and absolutely requires GTP hydrolysis. This concurs with the subsecond lifetime of active transducin and means that, once GTP hydrolysis has occurred, the hitherto active PDE is quickly inhibited. PMID:1658789

  8. 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.

  9. 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…

  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. Ground-water monitoring compliance projects for Hanford Site facilities: Annual progress report for 1987

    SciTech Connect

    Hall, S.H.

    1988-09-01

    This report describes progress during 1987 of five Hanford Site ground water monitoring projects. Four of these projects are being conducted according to regulations based on the federal Resource Conservation and Recovery Act of 1976 and the state Hazardous Waste Management Act. The fifth project is being conducted according to regulations based on the state Solid Waste Management Act. The five projects discussed herein are: 300 Area Process Trenches; 183-H Solar Evaporation Basins; 200 Areas Low-Level Burial Grounds; Nonradioactive Dangerous Waste Landfill; Solid Waste Landfill. For each of the projects, there are included, as applicable, discussions of monitoring well installations, water-table measurements, background and/or downgradient water quality and results of chemical analysis, and extent and rate of movement of contaminant plumes. 14 refs., 30 figs., 13 tabs.

  13. 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…

  14. 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)

  15. 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...

  16. The Utilization and Design of Physical Facilities for the Rehabilitation of Mentally Retarded. Final Project Report.

    ERIC Educational Resources Information Center

    Bair, Howard V.; Leland, Henry

    To investigate the appropriate design and utilization of physical facilities being constructed as a rehabilitation center, a variety of centers was examined. Conclusions were that flexibility in construction of the physical plant, including nonpermanent walls and fixtures was necessary; program planning should be included in architectural…

  17. 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

  18. 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

  19. 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.

  20. 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.

  1. Environmental studies in support of the live fire training facilities project

    SciTech Connect

    Hylton, T.D.; Walker, J.F.

    1989-08-01

    The Engineering Division of the Oak Ridge National Laboratory of Martin Marietta Energy System, Inc., provided services, under an Interagency Agreement, to the US Air Force to design, construct, and test environmentally acceptable fire training facilities at several Air Force bases for the purpose of providing live fire training capabilities without harming the environment. The purpose of this effort was to evaluate the wastewater treatment systems of the training facilities. The study focused on taking a set of background samples at a facility and then allowing the Air Force to conduct a series of training exercises. A set of samples was taken immediately following the training exercises to determine the effect the exercises had on the wastewater in the fuel/water separator and the holding pond. The separator and pond were also allowed to set undisturbed, except for sampling and environmental influences, for /approximately/60 d to determine if any stripping or biodegradation was occurring. Samples of the separator and pond were taken at 2, 4, 6, 8, 10, 11, 32, and 59 d following the training exercises. In addition, the burn pit was sampled immediately following the extinguishment of a fire and then again after the burn pit was flushed with water to determine if the materials remaining could be classified as hazardous under the Resource Conservation and Recovery Act (RCRA). 16 figs., 11 tabs.

  2. 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.

  3. 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

  4. Position measurements for the isotope production facility and the switchyard kicker upgrade projects

    SciTech Connect

    Gilpatrick, J. D.; Barr, D. S.; O'Hara, J. F.; Shurter, R. B.; Stettler, M. W.; Martinez, D. G.

    2003-01-01

    The Los Alamos Neutron Science Center (LANSCE) is installing two beam lines to both improve operational tuning and provide new capabilities within the facility. The Isotope Production Facility (IPF) will provide isotopes for medical purposes by using the H' beam spur at 100 MeV and the Switchyard Kicker Upgrade (SYK) will allow the LANSCE 800-MeV H beam to be rapidly switched between various beam lines within the facility. The beam position measurements for both of these beam lines uses a standard micro-stripline beam position monitor (BPM) with both a 50-mm and 75-mm radius. The cable plant is unique in that it unambiguously provides a method of verifying the operation of the complete position measurement. The processing electronics module uses a log ratio technique with error corrections such that it has a dynamic range of -12 dBm to -85 dBm with errors less than 0.15 dB within this range. This paper will describe the primary components of these measurement systems and provide initial data of their operation.

  5. The International Remote Monitoring Project: Results of the Swedish Nuclear Power Facility field trial

    SciTech Connect

    Johnson, C.S.; af Ekenstam, G.; Sallstrom, M.

    1995-07-01

    The Swedish Nuclear Power Inspectorate (SKI) and the US Department of Energy (DOE) sponsored work on a Remote Monitoring System (RMS) that was installed in August 1994 at the Barseback Works north of Malmo, Sweden. The RMS was designed to test the front end detection concept that would be used for unattended remote monitoring activities. Front end detection reduces the number of video images recorded and provides additional sensor verification of facility operations. The function of any safeguards Containment and Surveillance (C/S) system is to collect information which primarily is images that verify the operations at a nuclear facility. Barseback is ideal to test the concept of front end detection since most activities of safeguards interest is movement of spent fuel which occurs once a year. The RMS at Barseback uses a network of nodes to collect data from microwave motion detectors placed to detect the entrance and exit of spent fuel casks through a hatch. A video system using digital compression collects digital images and stores them on a hard drive and a digital optical disk. Data and images from the storage area are remotely monitored via telephone from Stockholm, Sweden and Albuquerque, NM, USA. These remote monitoring stations operated by SKI and SNL respectively, can retrieve data and images from the RMS computer at the Barseback Facility. The data and images are encrypted before transmission. This paper presents details of the RMS and test results of this approach to front end detection of safeguard activities.

  6. 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

  7. Project OPTEX: Field study at a petrochemical facility to assess optical remote sensing and dispersion modeling techniques

    SciTech Connect

    Paien, R.J.; Zwicker, J.O.; Feldman, H.

    1997-12-31

    The American Petroleum Inst. has conducted a field study at a petrochemical facility for the purpose of (1) testing the ability of optical remote sensing (ORS) techniques to characterize fugitive emissions, and (2) assembling ambient and tracer sampler data for evaluating air dispersion models. The study, referred to as the OPTEX (Operational Petrochemical Tracer Experiment) Project, took place during October 1996 at a Texas petrochemical facility. This paper reports on the design of the field study and summarizes the measurements that were obtained in the field. Several aspects of the field study are described in the paper: the types and locations of the emission releases and tracer gases that were used, the deployment of tracer samplers at various downwind distances, the use of open-path FTIR (OP-FTIR) equipment at the site to quantify tracer gas emissions, special short-term tracer gas emissions designed to test the ability of the ORS systems to detect accidental releases, and the use of a Doppler sodar to evaluate vertical profiles of wind and turbulence upwind and downwind of the facility. The data base for this study, as well as that from an earlier field study that took place at the Duke Forest green field site in North Carolina, will be used for evaluating air dispersion model performance and the ability of ORS measurements to quantify fugitive emissions.

  8. 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.

  9. 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.

  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. 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.

  14. Delayed fluorescence during the deactivation of highly excited triplet states

    SciTech Connect

    Skvortsov, V.I.; Alfimov, M.V.

    1987-06-01

    It has been suggested that the T state may be not only an electron donor but an acceptor, i.e., it may give a charge transfer state in a photoreduction reaction: A(T) + M ..-->.. /sup 3/(A/sup .-/M/sup +./). In this connection, it may be assumed that the quenching may also be connected with the nonradiative deactivation of excitation energy in charge transfer states (A/sup .-/M/sup +./). Aromatic molecules are characterized by an extremely low quantum yield for intramolecular intersystem crossing. However, in charge-transfer states the efficiency of intersystem crossing may be enhanced. The authors have investigated the laws governing DF in conditions where the deactivation of T states occurs. The systems studied were frozen (77 K) solutions of the aromatic additives naphthalene, diphenyl, and chrysene in toluene, MCH, and ethanol.

  15. 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

  16. 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.

  17. 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.

  18. Status of the SHIPTRAP Project: A Capture and Storage Facility for Heavy Radionuclides fromSHIP

    NASA Astrophysics Data System (ADS)

    Marx, G.; Ackermann, D.; Dilling, J.; Hessberger, F. P.; Hoffmann, S.; Kluge, H.-J.; Mann, R.; Münzenberg, G.; Qamhieh, Z.; Quint, W.; Rodriguez, D.; Schädel, M.; Schönfelder, J.; Sikler, G.; Toader, C.; Weber, C.; Engels, O.; Habs, D.; Thirolf, P.; Backe, H.; Dretzke, A.; Lauth, W.; Ludolphs, W.; Sewtz, M.

    2001-01-01

    The ion trap facility SHIPTRAP is being set up to deliver very clean and cool beams of singly-charged recoil ions produced at the SHIP velocity filter at GSI Darmstadt. SHIPTRAP consists of a gas cell for stopping and thermalizing high-energy recoil ions from SHIP, an rf ion guide for extraction of the ions from the gas cell, a linear rf trap for accumulation and bunching of the ions, and a Penning trap for isobaric purification. The progress in testing the rf ion guide is reported. A transmission of about 93(5)% was achieved.

  19. 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.

  20. 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.

  1. ZnS nano-architectures: photocatalysis, deactivation and regeneration.

    PubMed

    Chen, Dagui; Huang, Feng; Ren, Guoqiang; Li, Dongsong; Zheng, Meng; Wang, Yongjing; Lin, Zhang

    2010-10-01

    An "infinite recycling" method for enhancing the durable applications of a ZnS nano-photocatalyst is shown. Based on the finding of thermodynamic stable nanophase of ZnS, we designed a strategy in which the deactivated ZnS nano-photocatalyst could be recovered into its original state. This ZnS photocatalyst can be used repeatedly without being released into environment as nano-waste. The strategy uses material highly efficiently and is environmentally friendly.

  2. 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…

  3. 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.

  4. 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

  5. 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

  6. 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.

  7. 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.

  8. 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

  9. The Atlas project -- A new pulsed power facility for high energy density physics experiments

    SciTech Connect

    Parsons, W.M.; Ballard, E.O.; Bartsch, R.R.

    1997-04-01

    Atlas is a facility being designed at Los Alamos National Laboratory (LANL) to perform high-energy-density experiments in support of weapon physics and basic research programs. It is designed to be an international user facility, providing experimental opportunities to researchers from national laboratories and academic institutions. For hydrodynamic experiments, it will be capable of achieving a pressure exceeding 30 Mbar in a several cubic centimeter volume. With the development of a suitable opening switch, it will be capable of producing more than 3 MJ of soft X-rays. The capacitor bank design consists of a 36 MJ array of 240 kV Marx modules. The system is designed to deliver a peak current of 45--50 MA with a 4--5-{micro}s rise time. The Marx modules are designed to be reconfigured to a 480-kV configuration for opening switch development. The capacitor bank is resistively damped to limit fault currents and capacitor voltage reversal. An experimental program for testing and certifying prototype components is currently underway. The capacitor bank design contains 300 closing switches. These switches are a modified version of a railgap switch originally designed for the DNA-ACE machines. Because of the large number of switches in the system, individual switch prefire rates must be less than 10{sup {minus}4} to protect the expensive target assemblies. Experiments are underway to determine if the switch-prefire probability can be reduced with rapid capacitor charging.

  10. [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…

  11. 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.

  12. 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.

  13. 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

  14. 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.

  15. 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.

  16. Status and Plans for the FLARE (Facility for Laboratory Reconnection Experiments) Project

    NASA Astrophysics Data System (ADS)

    Ji, H.; Bhattacharjee, A.; Prager, S.; Daughton, W.; Bale, S.; Carter, T.; Crocker, N.; Drake, J.; Egedal, J.; Sarff, J.; Wallace, J.; Chen, Y.; Cutler, R.; Fox, W.; Heitzenroeder, P.; Kalish, M.; Jara-Almonte, J.; Myers, C.; Ren, Y.; Yamada, M.; Yoo, J.

    2015-11-01

    The FLARE device (flare.pppl.gov) is a new intermediate-scale plasma experiment under construction at Princeton to study magnetic reconnection in regimes directly relevant to space, solar, astrophysical, and fusion plasmas. The existing small-scale experiments have been focusing on the single X-line reconnection process either with small effective sizes or at low Lundquist numbers, but both of which are typically very large in natural and fusion plasmas. The design of the FLARE device is motivated to provide experimental access to the new regimes involving multiple X-lines, as guided by a reconnection ``phase diagram'' [Ji & Daughton, PoP (2011)]. Most of major components of the FLARE device have been designed and are under construction. The device will be assembled and installed in 2016, followed by commissioning and operation in 2017. The planned research on FLARE as a user facility will be discussed. Supported by NSF.

  17. 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)

  18. Results of the combustion and emissions research project at the Vicon Incinerator Facility in Pittsfield, Massachusetts: Final report, Volume 1

    SciTech Connect

    Not Available

    1987-06-01

    The New York State Energy Research Development Authority (Energy Authority) contracted with Midwest Research Institute (MRI) to conduct a series of tests at the Municipal Solid Waste incineration facility operated by VICON Recovery Associates in Pittsfield, Massaschusetts. The project was conducted in two phases. This final report presents the results of Phase II. Phase II was directed to the monitoring of combustion variables and to the sampling and analysis of polychlorinated dibenzo-p-dioxins, polychlorianted dibenzofurans, polychlorinated biphenyls, chlorobenzenes, chlorophenols, and polynuclear aromatic hydrocarbons in the combustion gases. Tests were conducted under several different incinerator operating conditions, including with different waste feeds, to identify any relationships between those compounds and the combustion variables and operating conditions.

  19. 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.

  20. 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.

  1. 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.

  2. The North West Shelf Project; Australian LNG facility ahead of schedule

    SciTech Connect

    Not Available

    1989-10-01

    The LNG complex, one of the most important natural resource developments ever undertaken in Australia, will provide a major new export industry for the country. It is based on vast hydrocarbon resources, primarily natural gas, discovered in the early 1970s on the North West Continental Shelf. The project consists of the North Rankin A gas drilling and production platform, a 70-mile subsea pipeline carrying the gas to shore, a domestic gas plant and three LNG trains. A second drilling and production platform, to be located in the Goodwyn field about 23 km from the North Rankin A platform, is now in the development stages. The complex is detailed in this paper.

  3. 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.

  4. 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.

  5. Considerations on Facilities Planning

    ERIC Educational Resources Information Center

    Baule, Steven

    2007-01-01

    Most facilities renovation projects occur because someone at the executive or board level has lobbied successfully for them. Often in public schools, the voters have agreed to the project as well via a building referendum. Therefore, facilities projects are highly visible to the community. Unlike many other issues in schools, facilities projects…

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. Variation in infection prevention practices in dialysis facilities: results from the national opportunity to improve infection control in ESRD (End-Stage Renal Disease) project.

    PubMed

    Chenoweth, Carol E; Hines, Stephen C; Hall, Kendall K; Saran, Rajiv; Kalbfleisch, John D; Spencer, Teri; Frank, Kelly M; Carlson, Diane; Deane, Jan; Roys, Erik; Scholz, Natalie; Parrotte, Casey; Messana, Joseph M

    2015-07-01

    OBJECTIVE To observe patient care across hemodialysis facilities enrolled in the National Opportunity to Improve Infection Control in ESRD (end-stage renal disease) (NOTICE) project in order to evaluate adherence to evidence-based practices aimed at prevention of infection. SETTING AND PARTICIPANTS Thirty-four hemodialysis facilities were randomly selected from among 772 facilities in 4 end-stage renal disease participating networks. Facility selection was stratified on dialysis organization affiliation, size, socioeconomic status, and urban/rural status. MEASUREMENTS Trained infection control evaluators used an infection control worksheet to observe 73 distinct infection control practices at the hemodialysis facilities, from October 1, 2011, through January 31, 2012. RESULTS There was considerable variation in infection control practices across enrolled facilities. Overall adherence to recommended practices was 68% (range, 45%-92%) across all facilities. Overall adherence to expected hand hygiene practice was 72% (range, 10%-100%). Compliance to hand hygiene before and after procedures was high; however, during procedures hand hygiene compliance averaged 58%. Use of chlorhexidine as the specific agent for exit site care was 19% overall but varied from 0% to 35% by facility type. The 8 checklists varied in the frequency of perfect performance from 0% for meeting every item on the checklist for disinfection practices to 22% on the arteriovenous access practices at initiation. CONCLUSIONS Our findings suggest that there are many areas for improvement in hand hygiene and other infection prevention practices in end-stage renal disease. These NOTICE project findings will help inform the development of a larger quality improvement initiative at dialysis facilities.

  11. 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

  12. 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.

  13. 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.

  14. 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).

  15. 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

  16. 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.

  17. Sulfur-deactivated steam reforming of gasified biomass

    SciTech Connect

    Koningen, J.; Sjoestroem, K.

    1998-02-01

    The effect of hydrogen sulfide on the stream reforming of methane has been studied. Methane is the most difficult component to convert by steam reforming in the mixture of hydrocarbons, which is produced in biomass gasification. Two catalysts were subjected to hydrogen sulfide levels up to 300 ppm so as to study the effect of sulfur on their deactivation. These catalysts were the C11-9-061, from United Catalyst Inc., and the HTSR1, from Haldor Topsoee. The activation energy of the sulfur-deactivated steam-reforming reaction was calculated to be 280 and 260 kJ/mol, for each catalyst, respectively. The high values most probably originate from the fact that the degree of sulfur coverage of the nickel surface is close to 1 for these experiments. Even under these severe conditions, steam reforming of methane is possible without any carbon formation. The HTSR1 catalyst exhibits a very high sulfur-free activity, resulting in a performance in the presence of hydrogen sulfide higher than that for the C11-9-061 catalyst. By using the HTSR1 catalyst, the reactor temperature can be lowered by 60 C in order to reach comparable levels of conversion.

  18. Helium Pot System for Maintaining Sample Temperature after Cryocooler Deactivation

    SciTech Connect

    Haid, B J

    2005-01-26

    A system for maintaining a sample at a constant temperature below 10K after deactivating the cooling source is demonstrated. In this system, the cooling source is a GM cryocooler that is joined with the sample through an adaptor that consists of a helium pot and a resistive medium. Upon deactivating the cryocooler, the power applied to a heater located on the sample side of the resistive medium is decreased gradually to maintain an appropriate temperature rise across the resistive medium as the helium pot warms. The 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 processes that are very sensitive to sample position stability, but are not performed throughout the duration that the sample is at low-temperature. An apparatus was constructed to demonstrate this technique using a 4K GM cryocooler. Experimental and theoretical predictions indicate that when the helium pot is pressurized to the working pressure of the cryocooler's helium supply, a sample with continuous heat dissipation of several-hundred milliwatts can be maintained at 7K for several minutes when using an extension that increases the cold head length by less than 50%.

  19. 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.

  20. 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.

  1. 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.

  2. 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…

  3. Preliminary Plans Presented for Construction of John F. Kennedy School and Community Center- 1966 Bond Fund Project No. PS42-62-785-7 and Neighborhood Facilities Grant Project No. GA. N-7.

    ERIC Educational Resources Information Center

    Atlanta Board of Education, GA.

    A proposed project which is a result of the cooperative efforts of many agencies is described. The planned facility will offer to residents of the community, a multitude of needed services which have never been brought together under one roof. The center will include a middle school of grades six to eight for approximately 1,050 students. The…

  4. Giving cell phones to pregnant women and improving services may increase primary health facility utilization: a case–control study of a Nigerian project

    PubMed Central

    2014-01-01

    Background Worldwide, about 287 000 women die each year from mostly preventable complications related to pregnancy and childbirth. A disproportionately high number of these deaths occur in sub-Saharan Africa. The Abiye (‘Safe Motherhood’) project in the Ifedore Local Government Area (LGA) of Ondo-State of Nigeria aimed at improving facility utilization and maternal health through the use of cell phones and generally improved health care services for pregnant women, including Health Rangers, renovated Health Centres, and improved means of transportation. Methods A one-year sample of retrospective data was collected from hospital records and patients’ case files from Ifedore (the project area) and Idanre (control area) and was analyzed to determine healthcare facility utilization rates in each location. Semi-structured questionnaires were used to generate supplemental data. Results The total facility utilization rate of pregnant women was significantly higher in Ifedore than in Idanre. The facility utilization rate of the primary health care centres was significantly higher in Ifedore than in Idanre. The number of recorded cases of the five major causes of maternal death in the two LGAs was not significantly different, possibly because the project was new. Conclusions Giving cell phones to pregnant women and generally improving services could increase their utilization of the primary healthcare system. PMID:24438150

  5. 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.

  6. Environmental restoration plan for the transfer of surplus facilities to the Facility Transition Program at Oak Ridge National Laboratory

    SciTech Connect

    1995-08-01

    This report will provide guidance on management, coordination, and integration of plans to transition facilities to the Facility Transition Program and activities as related to the Oak Ridge National Laboratory (ORNL) Environmental Restoration Program facilities. This report gives (1) guidance on the steps necessary for identifying ORNL surplus facilities, (2) interfaces of Surveillance and Maintenance (S and M) and Isotope Facility Deactivation program managers, (3) roles and responsibilities of the facility managers, and (4) initial S and M requirements upon acceptance into the Facility Transition Program.

  7. Epidemics with temporary link deactivation in scale-free networks.

    PubMed

    Shkarayev, Maxim S; Tunc, Ilker; Shaw, Leah B

    2014-11-14

    During an epidemic, people may adapt or alter their social contacts to avoid infection. Various adaptation mechanisms have been studied previously. Recently, a new adaptation mechanism was presented in [1], where susceptible nodes temporarily deactivate their links to infected neighbors and reactivate when their neighbors recover. Considering the same adaptation mechanism on a scale-free network, we find that the topology of the subnetwork consisting of active links is fundamentally different from the original network topology. We predict the scaling exponent of the active degree distribution and derive mean-field equations by using improved moment closure approximations based on the conditional distribution of active degree given the total degree. These mean field equations show better agreement with numerical simulation results than the standard mean field equations based on a homogeneity assumption.

  8. Revealing Deactivation Pathways Hidden in Time-Resolved Photoelectron Spectra

    PubMed Central

    Ruckenbauer, Matthias; Mai, Sebastian; Marquetand, Philipp; González, Leticia

    2016-01-01

    Time-resolved photoelectron spectroscopy is commonly employed with the intention to monitor electronic excited-state dynamics occurring in a neutral molecule. With the help of theory, we show that when excited-state processes occur on similar time scales the different relaxation pathways are completely obscured in the total photoionization signal recorded in the experiment. Using non-adiabatic molecular dynamics and Dyson norms, we calculate the photoionization signal of cytosine and disentangle the transient contributions originating from the different deactivation pathways of its tautomers. In the simulations, the total signal from the relevant keto and enol tautomers can be decomposed into contributions either from the neutral electronic state populations or from the distinct mechanistic pathways across the multiple potential surfaces. The lifetimes corresponding to these contributions cannot be extracted from the experiment, thereby illustrating that new experimental setups are necessary to unravel the intricate non-adiabatic pathways occurring in polyatomic molecules after irradiation by light. PMID:27762396

  9. Epidemics with temporary link deactivation in scale-free networks

    NASA Astrophysics Data System (ADS)

    Shkarayev, Maxim S.; Tunc, Ilker; Shaw, Leah B.

    2014-11-01

    During an epidemic, people may adapt or alter their social contacts to avoid infection. Various adaptation mechanisms have been studied previously. Recently, a new adaptation mechanism was presented in (Tunc et al 2013 J. Stat. Phys. 151 355), where susceptible nodes temporarily deactivate their links to infected neighbors and reactivate when their neighbors recover. Considering the same adaptation mechanism on a scale-free network, we find that the topology of the subnetwork consisting of active links is fundamentally different from the original network topology. We predict the scaling exponent of the active degree distribution and derive mean field equations by using improved moment closure approximations based on the conditional distribution of active degree given the total degree. These mean field equations show better agreement with numerical simulation results than the standard mean field equations based on a homogeneity assumption.

  10. Ultrafast electronic deactivation dynamics of the rare natural nucleobase hypoxanthine

    NASA Astrophysics Data System (ADS)

    Röttger, Katharina; Siewertsen, Ron; Temps, Friedrich

    2012-05-01

    The electronic deactivation of the 6-oxopurine derivative hypoxanthine, its nucleoside inosine and the nucleotide inosine monophosphate have been studied by femtosecond time-resolved spectroscopy after ππ∗ photoexcitation at λ = 260 nm. The development of a highly sensitive parallel broadband (near-UV/VIS) and single-color (deep-UV) transient absorption setup enabled us to monitor the excited-state decay and the ground-state recovery dynamics in one and the same experiment. The measurements revealed similar relaxation behavior, with time constants of τ1 ≲ 0.1 ps, τ2 ≈ 0.21 ± 0.08 ps and τ3 ≈ 1.8 ± 0.4 ps, for all three investigated molecules. The observed dynamics are assumed to take place through a conical intersection involving an out-of-plane puckering mode of the six-membered ring similar to guanine.

  11. Epidemics with temporary link deactivation in scale-free networks

    PubMed Central

    Shkarayev, Maxim S.; Tunc, Ilker; Shaw, Leah B.

    2014-01-01

    During an epidemic, people may adapt or alter their social contacts to avoid infection. Various adaptation mechanisms have been studied previously. Recently, a new adaptation mechanism was presented in [1], where susceptible nodes temporarily deactivate their links to infected neighbors and reactivate when their neighbors recover. Considering the same adaptation mechanism on a scale-free network, we find that the topology of the subnetwork consisting of active links is fundamentally different from the original network topology. We predict the scaling exponent of the active degree distribution and derive mean-field equations by using improved moment closure approximations based on the conditional distribution of active degree given the total degree. These mean field equations show better agreement with numerical simulation results than the standard mean field equations based on a homogeneity assumption. PMID:25419231

  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. 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.

  14. The User Community and a Multi-Mission Data Project: Services, Experiences and Directions of the Space Physics Data Facility

    NASA Astrophysics Data System (ADS)

    McGuire, R.; Bilitza, D.; Candey, R.; Chimiak, R.; Cooper, J.; Fung, S.; Harris, B.; Johnson, R.; King, J.; Kovalick, T.; Leckner, H.; Papitashvili, N.; Roberts, D. A.

    2008-05-01

    From a science user's perspective, the multi-mission data and orbit services of NASA's Space Physics Data Facility (SPDF) project offers a unique range of important data and services directly supporting the Heliophysics Great Observatory and highly complementary to other services presently available or now evolving in the international heliophysics data environment. The VSPO (Virtual Space Physics Observatory) service is an active portal to a wide range of distributed data sources. CDAWeb (Coordinated Data Analysis Web) enables plots, listings and file downloads for current data across 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 format translation services. These capabilities are all now available through webservices-based APIs, one element in SPDF's ongoing work to enable heliophysics community development of Virtual discipline Observatories and the ready attachment of SPDF services into those 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 our current thinking to the future role and appropriate focus of the SPDF effort in the evolving and increasingly distributed heliophysics data environment.

  15. 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.

  16. 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.

  17. 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)

  18. 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

  19. 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.

  20. 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.

  1. 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…

  2. 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.

  3. On the problem of deactivation of land areas contaminated with radionuclides

    SciTech Connect

    Blagoev, V.V.; Galkin, A.P.; Galkina, L.A.

    1996-12-31

    This paper describes a complex of technologies for land deactivation in areas of nuclear accidents, short-term chemical fixation of such dusting areas as well as long-term combined chemical and biological fixation. Short-term fixation is based on application of chemical compositions containing side-products of hydrolysis of cellulose and calcium chloride. Long-term fixation is achieved by application of some plants that are able to intensive growth. These combined covers prevent an expansion of radionuclides into environment. Methods of deactivation include removal of surface layer of soil with following displacement or burial. Effective deactivation is provided by available technics and cheep chemicals.

  4. 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.

  5. 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.

  6. 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.

  7. Excited-State Deactivation of Branched Phthalocyanine Compounds.

    PubMed

    Zhu, Huaning; Li, Yang; Chen, Jun; Zhou, Meng; Niu, Yingli; Zhang, Xinxing; Guo, Qianjin; Wang, Shuangqing; Yang, Guoqiang; Xia, Andong

    2015-12-21

    The excited-state relaxation dynamics and chromophore interactions in two phthalocyanine compounds (bis- and trisphthalocyanines) are studied by using steady-state and femtosecond transient absorption spectral measurements, where the excited-state energy-transfer mechanism is explored. By exciting phthalocyanine compounds to their second electronically excited states and probing the subsequent relaxation dynamics, a multitude of deactivation pathways are identified. The transient absorption spectra show the relaxation pathway from the exciton state to excimer state and then back to the ground state in bisphthalocyanine (bis-Pc). In trisphthalocyanine (tris-Pc), the monomeric and dimeric subunits are excited and the excitation energy transfers from the monomeric vibrationally hot S1 state to the exciton state of a pre-associated dimer, with subsequent relaxation to the ground state through the excimer state. The theoretical calculations and steady-state spectra also show a face-to-face conformation in bis-Pc, whereas in tris-Pc, two of the three phthalocyanine branches form a pre-associated face-to-face dimeric conformation with the third one acting as a monomeric unit; this is consistent with the results of the transient absorption experiments from the perspective of molecular structure. The detailed structure-property relationships in phthalocyanine compounds is useful for exploring the function of molecular aggregates in energy migration of natural photosynthesis systems.

  8. 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.

  9. Soluble inhibitors/deactivators of cellulase enzymes from lignocellulosic biomass.

    PubMed

    Kim, Youngmi; Ximenes, Eduardo; Mosier, Nathan S; Ladisch, Michael R

    2011-04-01

    Liquid hot water, steam explosion, and dilute acid pretreatments of lignocellulose generate soluble inhibitors which hamper enzymatic hydrolysis as well as fermentation of sugars to ethanol. Toxic and inhibitory compounds will vary with pretreatment and include soluble sugars, furan derivatives (hydroxymethyl fulfural, furfural), organic acids (acetic, formic and, levulinic acid), and phenolic compounds. Their effect is seen when an increase in the concentration of pretreated biomass in a hydrolysis slurry results in decreased cellulose conversion, even though the ratio of enzyme to cellulose is kept constant. We used lignin-free cellulose, Solka Floc, combined with mixtures of soluble components released during pretreatment of wood, to prove that the decrease in the rate and extent of cellulose hydrolysis is due to a combination of enzyme inhibition and deactivation. The causative agents were extracted from wood pretreatment liquid using PEG surfactant, activated charcoal or ethyl acetate and then desorbed, recovered, and added back to a mixture of enzyme and cellulose. At enzyme loadings of either 1 or 25mg protein/g glucan, the most inhibitory components, later identified as phenolics, decreased the rate and extent of cellulose hydrolysis by half due to both inhibition and precipitation of the enzymes. Full enzyme activity occurred when the phenols were removed. Hence detoxification of pretreated woods through phenol removal is expected to reduce enzyme loadings, and therefore reduce enzyme costs, for a given level of cellulose conversion.

  10. 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.

  11. 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.

  12. 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

  13. 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.

  14. Microwave-driven enzyme deactivation using imidazolium salt-presenting silica nanoparticles.

    PubMed

    Okada, Hiroshi; Tanaka, Kazuo; Chujo, Yoshiki

    2014-10-01

    Thermal enzyme deactivation by the imidazolium-presenting silica nanoparticles with the microwave irradiation is presented in this manuscript. The modified nanoparticles were synthesized, and it was observed that the modified nanoparticles can be a heat source in the buffer under the weak-power microwave irradiation. Finally, based on the heat-generating ability of these nanoparticles, deactivation of glutathione reductase and alkaline phosphatase with the modified nanoparticles were demonstrated. PMID:25223957

  15. 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.

  16. 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.

  17. Deactivating Cochlear Implant Electrodes Based on Pitch Information for Users of the ACE Strategy.

    PubMed

    Vickers, Deborah; Degun, Aneeka; Canas, Angela; Stainsby, Thomas; Vanpoucke, Filiep

    2016-01-01

    There is a wide range in performance for cochlear implant (CI) users and there is some evidence to suggest that implant fitting can be modified to improve performance if electrodes that do not provide distinct pitch information are de-activated. However, improvements in performance may not be the same for users of all CI devices; in particular for those with Cochlear devices using n-of-m strategies (ACE or SPEAK).The goal of this research was to determine for users of Cochlear devices (CP810 or CP900 series processors) if speech perception could be improved when indiscriminable electrodes were de-activated and this was also compared to when the same number of discriminable electrodes were de-activated.A cross-over study was conducted with 13 adult CI users who received experimental maps with de-activated channels for a minimum of 2 months and these were compared to optimised clinical maps.The findings showed that there were no significant benefits of electrode de-activation on speech perception and that there was a significant deterioration in spectro-temporal ripple perception when electrodes were switched off. There were no significant differences between de-activation of discriminable or indiscriminable electrodes.These findings suggest that electrode de-activation with n-of-m strategies may not be beneficial. PMID:27080652

  18. 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.

  19. Deactivating Cochlear Implant Electrodes Based on Pitch Information for Users of the ACE Strategy.

    PubMed

    Vickers, Deborah; Degun, Aneeka; Canas, Angela; Stainsby, Thomas; Vanpoucke, Filiep

    2016-01-01

    There is a wide range in performance for cochlear implant (CI) users and there is some evidence to suggest that implant fitting can be modified to improve performance if electrodes that do not provide distinct pitch information are de-activated. However, improvements in performance may not be the same for users of all CI devices; in particular for those with Cochlear devices using n-of-m strategies (ACE or SPEAK).The goal of this research was to determine for users of Cochlear devices (CP810 or CP900 series processors) if speech perception could be improved when indiscriminable electrodes were de-activated and this was also compared to when the same number of discriminable electrodes were de-activated.A cross-over study was conducted with 13 adult CI users who received experimental maps with de-activated channels for a minimum of 2 months and these were compared to optimised clinical maps.The findings showed that there were no significant benefits of electrode de-activation on speech perception and that there was a significant deterioration in spectro-temporal ripple perception when electrodes were switched off. There were no significant differences between de-activation of discriminable or indiscriminable electrodes.These findings suggest that electrode de-activation with n-of-m strategies may not be beneficial.

  20. 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.

  1. 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.

  2. 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.

  3. 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

  4. Operator awareness of system status during Fast Flux Test Facility transition to standby

    SciTech Connect

    Gibson, J.L.

    1994-04-01

    A facility in transition, due to a change in its mission or its operating status, begins to depart from a previously well-defined normal mode of operation. The equipment becomes reconfigured or deactivated. In an environment of transition, the Fast Flux Test Facility (FFTF) has employed methods to enhance operator awareness of system status. These methods are described in this report.

  5. 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…

  6. 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

  7. 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…

  8. 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.

  9. Mentally Retarded People in State-Operated Residential Facilities: Year Ending June 30, 1979. Project Report No. 8.

    ERIC Educational Resources Information Center

    Krantz, Gordon C., Comp.; And Others

    Data from a nationwide survey of mentally retarded people in state operated residential institutions are presented. Findings are listed for 22 aspects, including number of facilities, average daily residents, new admissions, readmissions during the year, deaths during the year, per diem cost, admissions ratios, termination ratios, net population…

  10. 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…

  11. 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.

  12. Stochastic modeling and control system designs of the NASA/MSFC Ground Facility for large space structures: The maximum entropy/optimal projection approach

    NASA Technical Reports Server (NTRS)

    Hsia, Wei-Shen

    1986-01-01

    In the Control Systems Division of the Systems Dynamics Laboratory of the NASA/MSFC, a Ground Facility (GF), in which the dynamics and control system concepts being considered for Large Space Structures (LSS) applications can be verified, was designed and built. One of the important aspects of the GF is to design an analytical model which will be as close to experimental data as possible so that a feasible control law can be generated. Using Hyland's Maximum Entropy/Optimal Projection Approach, a procedure was developed in which the maximum entropy principle is used for stochastic modeling and the optimal projection technique is used for a reduced-order dynamic compensator design for a high-order plant.

  13. Methods for Valuation of Environmental Costs and Benefits of Hydroelectric Facilities : A Case Study of the Sultan River Project : Final Report.

    SciTech Connect

    BioSystems Analysis, Inc.

    1984-06-05

    The Bonneville Power Administration is required by the Pacific Northwest Electric Power Planning and Conservation Act (Public Law 96-501) to include quantifiable environmental costs and benefits of alternative electric power resources in determining their cost-effectiveness. In responding to this requirement, BPA has contracted to develop and test methodologies for valuing environmental costs of various types of power resources, including hydroelectric facilities. The purpose of this study is to develop and test valuation methods for hydroelectric facilities, using the Sultan River Project as a case study. The case study approach offers several advantages and some disadvantages which should be considered in interpreting this report. Its primary advantage lies in providing a real-world example against which to test theoretical valuation approaches. Using data that were actually collected for a project that has received detailed scrutiny from its sponsor and from numerous regulatory agencies allows more realistic formulation of valuation issues and also provides a better test of the practicality and usefulness of valuation methods. On the other hand, results derived from such an approach must be used with discretion. First and most obvious, both the features of a hydroproject and its environmental impacts may vary widely from site to site. Second, it cannot be assumed that the results of these test exercises for the Sultan River Project represent any kind of generic hydroelectric environmental cost. A third caution is directed to those who may be tempted to regard this report as a definitive estimate of the environmental costs of the Sultan River Project. It is not. A fourth important point is only external or residual environmental costs are developed in this report. Finally, it should be noted that these methodologies were developed to meet the needs of BPA's process for determining resource cost-effectiveness.

  14. Allowing for MSD prevention during facilities planning for a public service: an a posteriori analysis of 10 library design projects.

    PubMed

    Bellemare, Marie; Trudel, Louis; Ledoux, Elise; Montreuil, Sylvie; Marier, Micheline; Laberge, Marie; Vincent, Patrick

    2006-01-01

    Research was conducted to identify an ergonomics-based intervention model designed to factor in musculoskeletal disorder (MSD) prevention when library projects are being designed. The first stage of the research involved an a posteriori analysis of 10 recent redesign projects. The purpose of the analysis was to document perceptions about the attention given to MSD prevention measures over the course of a project on the part of 2 categories of employees: librarians responsible for such projects and personnel working in the libraries before and after changes. Subjects were interviewed in focus groups. Outcomes of the analysis can guide our ergonomic assessment of current situations and contribute to a better understanding of the way inclusion or improvement of prevention measures can support the workplace design process.

  15. Conceptual design statement of work for the immobilized low-activity waste disposal facility, project W-520

    SciTech Connect

    Pickett, W.W.

    1998-04-30

    This Statement of Work outlines the deliverables and schedule for preparation of the Project W-520 Conceptual Design Report, including, work plans, site development plan, preliminary safety evaluation, and conceptual design.

  16. ENVIRONMENTAL MANAGEMENT SCIENCE PROGRAM RESEARCH PROJECTS TO IMPROVE DECONTAMINATION AND DECOMMISIONING OF U.S. DEPARTMENT OF ENERGY FACILITIES

    SciTech Connect

    Phillips, Ann Marie

    2003-02-27

    This paper describes fourteen basic science projects aimed at solving decontamination and decommissioning (D&D) problems within the U.S. Department of Energy (DOE). Funded by the Environmental Science Management Program (EMSP), these research projects address D&D problems where basic science is needed to expand knowledge and develop solutions to help DOE meet its cleanup milestones. EMSP uses directed solicitations targeted at identified Environmental Management (EM) needs to ensure that research results are directly applicable to DOE's EM problems. The program then helps transition the projects from basic to applied research by identifying end-users and coordinating proof-of-principle field tests. EMSP recently funded fourteen D&D research projects through the directed solicitation process. These research projects will be discussed, including description, current status, and potential impact. Through targeted research and proof-of-principle tests, it is hoped that EMSP's fourteen D&D basic research projects will directly impact and provide solutions to DOE's D&D problems.

  17. Plutonium Consumption Program, CANDU Reactor Project: Feasibility of BNFP Site as MOX Fuel Supply Facility. Final report

    SciTech Connect

    1995-06-30

    An evaluation was made of the technical feasibility, cost, and schedule for converting the existing unused Barnwell Nuclear Fuel Facility (BNFP) into a Mixed Oxide (MOX) CANDU fuel fabrication plant for disposition of excess weapons plutonium. This MOX fuel would be transported to Ontario where it would generate electricity in the Bruce CANDU reactors. Because CANDU MOX fuel operates at lower thermal load than natural uranium fuel, the MOX program can be licensed by AECB within 4.5 years, and actual Pu disposition in the Bruce reactors can begin in 2001. Ontario Hydro will have to be involved in the entire program. Cost is compared between BNFP and FMEF at Hanford for converting to a CANDU MOX facility.

  18. Small-Scale Hydroelectric Power Demonstration Project: reactivation of the Elk Rapids Hydroelectric Facility. Final technical and construction cost report

    SciTech Connect

    Not Available

    1985-05-01

    The Elk Rapids powerhouse dam is located on the Elk River channel in the Village of Elk Rapids, Michigan. Together with a small spillway structure located approximately 500 ft south of the dam, it constitutes the outlet to Lake Michigan for Elk Lake, Skegemog Lake, Torch Lake, Lake Bellaire, Clam Lake, and several smaller lakes. Power has been generated at the Elk Rapids site since the late nineteenth century, but the history of the present facility goes back to 1916 with the construction of the existing powerhouse dam by the Elk Rapids Iron Works Company. The facility was designed to contain four vertical-shaft generating units; however, only a single 270 hp Leffel type K unit was installed in 1916. In 1929, two additional Leffel units, rated 525 hp, were installed, and in 1930 a third 525 hp Leffel unit was added completely utilizing the capacity of the powerhouse and bringing the combined turbine capacity to 1845 hp.

  19. Performance of a liquid argon time projection chamber exposed to the CERN West Area Neutrino Facility neutrino beam

    SciTech Connect

    Arneodo, F.; Cavanna, F.; Mitri, I. De; Mortari, G. Piano; Benetti, P.; Borio di Tigliole, A.; Calligarich, E.; Cesana, E.; Dolfini, R.; Mauri, F.; Montanari, C.; Rappoldi, A.; Raselli, G. L.; Rubbia, C.; Terrani, M.; Vignoli, C.; Bonesini, M.; Boschetti, B.; Cavalli, D.; Curioni, A.

    2006-12-01

    We present the results of the first exposure of a Liquid Argon TPC to a multi-GeV neutrino beam. The data have been collected with a 50 liters ICARUS-like chamber located between the CHORUS and NOMAD experiments at the CERN West Area Neutrino Facility (WANF). We discuss both the instrumental performance of the detector and its capability to identify and reconstruct low-multiplicity neutrino interactions.

  20. Biological restoration of major transportation facilities domestic demonstration and application project (DDAP): technology development at Sandia National Laboratories.

    SciTech Connect

    Ramsey, James L., Jr.; Melton, Brad; Finley, Patrick; Brockman, John; Peyton, Chad E.; Tucker, Mark David; Einfeld, Wayne; Griffith, Richard O.; Brown, Gary Stephen; Lucero, Daniel A.; Betty, Rita G.; McKenna, Sean Andrew; Knowlton, Robert G.; Ho, Pauline

    2006-06-01

    The Bio-Restoration of Major Transportation Facilities Domestic Demonstration and Application Program (DDAP) is a designed to accelerate the restoration of transportation nodes following an attack with a biological warfare agent. This report documents the technology development work done at SNL for this DDAP, which include development of the BROOM tool, an investigation of surface sample collection efficiency, and a flow cytometry study of chlorine dioxide effects on Bacillus anthracis spore viability.

  1. The fast-spectrum transmutation experimental facility FASTEF: Main design achievements (Part 1: Core and primary system) within the FP7-CDT collaborative project of the European Commission

    SciTech Connect

    De Bruyn, D.; Fernandez, R.; Mansani, L.; Woaye-Hune, A.; Sarotto, M.; Bubelis, E.

    2012-07-01

    MYRRHA (Multi-purpose hybrid Research Reactor for High-tech Applications) is the flexible experimental accelerator-driven system (ADS) in development at SCK CEN in replacement of its material testing reactor BR2. SCK CEN in association with 17 European partners from industry, research centres and academia, responded to the FP7 (Seventh Framework Programme) call from the European Commission to establish a Central Design Team (CDT) for the design of a Fast Spectrum Transmutation Experimental Facility (FASTEF) able to demonstrate efficient transmutation and associated technology through a system working in subcritical and/or critical mode. The project has started on April 01, 2009 for a period of three years. In this paper, we present the latest configuration of the reactor core and primary system. The FASTEF facility has evolved quite a lot since the intermediate reporting done at the ICAPP'10 and ICAPP'11 conferences 1 2. If it remains a small-scale facility, the core power amounts now up to 100 MWth in critical mode. In a companion paper 3, we present the concept of the reactor building and the plant layout. (authors)

  2. Ground-water monitoring compliance projects for Hanford Site facilities: Progress Report for the Period July 1 to September 30, 1987

    SciTech Connect

    Not Available

    1987-11-01

    This report documents the progress of four Hanford Site ground-water monitoring projects for the period from July 1 to September 310, 1987. The four disposal facilities are the 300 Area Process Trenches, 183-H Solar Evaporation Basins, 200 Area Low-Level Burial Grounds, and Nonradioactive Dangerous Waste (NRDW) Landfill. This report is the fifth in a series of periodic status reports. During this reporting period, field activities consisted of completing repairs on five monitoring wells originally present around the 183-H Basins and completing construction of 25 monitoring wells around the 200 Area Burial Grounds. The 14 wells in the 200 East Area were completed by Kaiser Engineers Hanford (KEH) and the 11 wells in the 200 West Area were compelted by ONWEGO Well Drilling. The NRDW Landfill interim characterization report was submitted to the WDOE and the USEPA in August 1987. Analytical results for the 300 Area, 183-H, and the NRDW Landfill indicate no deviations from previously established trends. Results from the NRDW Land-fill indiate that the facility has no effect on the ground-water quality beneath the facility, except for the detection of coliform bacteria. A possible source of this contamination is the solid-waste lanfill (SWL) adjacent to the NRDW Landfill. Ground-water monitoring data for the NRDW and SWL will be evaluated together in the future. Aquifer testing was completed in the 25 new wells surrounding the 200 Area buiral grounds. 13 refs., 19 refs., 13 tabs.

  3. Geologic evaluation of six nonwelded tuff sites in the vicinity of Yucca Mountain, Nevada for a surface-based test facility for the Yucca Mountain Project

    SciTech Connect

    Broxton, D.E.; Chipera, S.J.; Byers, F.M. Jr.; Rautman, C.A.

    1993-10-01

    Outcrops of nonwelded tuff at six locations in the vicinity of Yucca Mountain, Nevada, were examined to determine their suitability for hosting a surface-based test facility for the Yucca Mountain Project. Investigators will use this facility to test equipment and procedures for the Exploratory Studies Facility and to conduct site characterization field experiments. The outcrops investigated contain rocks that include or are similar to the tuffaceous beds of Calico Hills, an important geologic and hydrologic barrier between the potential repository and the water table. The tuffaceous beds of Calico Hills at the site of the potential repository consist of both vitric and zeolitic tuffs, thus three of the outcrops examined are vitric tuffs and three are zeolitic tuffs. New data were collected to determine the lithology, chemistry, mineralogy, and modal petrography of the outcrops. Some preliminary data on hydrologic properties are also presented. Evaluation of suitability of the six sites is based on a comparison of their geologic characteristics to those found in the tuffaceous beds of Calico Hills within the exploration block.

  4. Submission of Notice of Termination of Coverage Under the National Pollutant Discharge Elimination System General Permit No. CAS000002 for WDID No. 201C349114, Lawrence Livermore National Laboratory Ignition Facility Construction Project

    SciTech Connect

    Brunckhorst, K

    2009-04-21

    This is the completed Notice of Termination of Coverage under the General Permit for Storm Water Discharges Associated with Construction Activity. Construction activities at the National Ignition Facility Construction Project at Lawrence Livermore National Laboratory are now complete. The Notice of Termination includes photographs of the completed construction project and a vicinity map.

  5. Viscous heating effect on deactivation of helminth eggs in ventilated improved pit sludge.

    PubMed

    Belcher, D; Foutch, G L; Smay, J; Archer, C; Buckley, C A

    2015-01-01

    Viscous heating by extrusion of faecal material obtained from ventilated improved pit (VIP) latrines can be used to deactivate soil-transmitted helminth (STH) eggs by increasing the temperature of faecal sludge uniformly. Viscous heating can deactivate STH eggs present in sludge to make the material safer to transport, dispose of, or use in agricultural applications or as an energy source. The mechanical energy required to generate the shear rate can originate from any source. No other heat source or additive is required. Here we determined a baseline for the deactivation of STH eggs using viscous heating. To characterize equipment performance, three parameters were investigated: (1) minimum temperature required for deactivation; (2) local maximum temperatures for various flow rates and moisture contents (MCs); and (3) thermal efficiency. Excess water is undesirable since low viscosities require extended residence time and increased energy input. The minimum temperature to achieve greater than 90% helminth egg deactivation is 70 °C. For the laboratory-scale equipment tested, the maximum allowable mass flow rate for VIP sludge with 77% MC was found to be 3.6 g/s.

  6. 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.

  7. Reversible deactivation radical polymerization mediated by cobalt complexes: recent progress and perspectives.

    PubMed

    Peng, Chi-How; Yang, Tsung-Yao; Zhao, Yaguang; Fu, Xuefeng

    2014-11-21

    Mediation of reversible deactivation radical polymerization (RDRP) by cobalt(II) complexes (CMRP) is the most highly developed subcategory of organometallic mediated RDRP (OMRP). Attention was paid to CMRP for its unusual high efficiency observed for the control of acrylate and vinyl acetate polymerization that produced homo- and block copolymers with narrow molecular weight distribution and a predictable molecular weight. The reactions of organic radicals with cobalt(II) metallo-radicals and organo-cobalt(III) complexes have a central role in the pathways that mediate this type of reversible deactivation radical polymerization. The reversible deactivation pathway dominates the polymerization when cobalt(II) complexes can reversibly deactivate the radicals to form organo-cobalt(III) complexes. Degenerative transfer becomes the major pathway when the cobalt(II) species fully convert to organo-cobalt(III) complexes and the radicals in solution rapidly exchange with radicals in organo-cobalt(III) complexes. This review describes the polymerization behavior and control mechanisms used by cobalt complexes in the mediation of reversible deactivation radical polymerization. The emerging developments for CMRP in the aqueous phase and with photo-initiation are also described, followed by the challenges and future applications of this method.

  8. Preliminary engineering report waste area grouping 5, Old Hydrofracture Facility Tanks content removal project, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1996-06-01

    The Superfund Amendments and Reauthorization Act of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requires a Federal Facilities Agreement (FFA) for federal facilities placed on the National Priorities List. The Oak Ridge Reservation was placed on that list on December 21, 1989, and the agreement was signed in November 1991 by the U.S. Department of Energy (DOE) Oak Ridge Operations Office, the U.S. Environmental Protection Agency (EPA) Region IV, and the Tennessee Department of Environment and Conservation (TDEC). The effective date of the FFA is January 1, 1992. One objective of the FFA is to ensure that liquid low-level waste (LLLW) tanks that are removed from service are evaluated and remediated through the CERCLA process. Five inactive LLLW tanks, designated T-1, T-2, T-3, T-4, and T-9, located at the Old Hydrofracture (OHF) Facility in the Melton Valley area of Oak Ridge National Laboratory (ORNL) have been evaluated and are now entering the remediation phase. As a precursor to final remediation, this project will remove the current liquid and sludge contents of each of the five tanks (System Requirements Document, Appendix A). It was concluded in the Engineering Evaluation/Cost Analysis [EE/CA] for the Old Hydrofracture Facility Tanks (DOE 1996) that sluicing and pumping the contaminated liquid and sludge from the five OHF tanks was the preferred removal action. Evaluation indicated that this alternative meets the removal action objective and can be effective, implementable, and cost-effective. Sluicing and removing the tank contents was selected because this action uses (1) applicable experience, (2) the latest information about technologies and techniques for removing the wastes from the tanks, and (3) activities that are currently acceptable for storage of transuranic (TRU) mixed waste.

  9. Finding of no significant impact for the tritium facility modernization and consolidation project at the Savannah River Site

    SciTech Connect

    1998-01-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-1222) for the proposed modernization and consolidation of the existing tritium facilities at the Savannah River Site (SRS), located near Aiken, South Carolina. Based on the analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (NEPA). Therefore, the preparation of an environmental impact statement (EIS) is not required, and DOE is issueing this Finding of No Significant Impact (FONSI).

  10. 'BioQuaRT' project: design of a novel in situ protocol for the simultaneous visualisation of chromosomal aberrations and micronuclei after irradiation at microbeam facilities.

    PubMed

    Patrono, C; Monteiro Gil, O; Giesen, U; Langner, F; Pinto, M; Rabus, H; Testa, A

    2015-09-01

    The aim of the 'BioQuaRT' (Biologically weighted Quantities in RadioTherapy) project is to develop measurement techniques for characterising charged particle track structure on different length scales, and to correlate at the cellular level the track structure properties with the biological effects of radiation. This multi-scale approach will allow characterisation of the radiation qualities used in radiotherapy and the related biological effects. Charged-particle microbeam facilities were chosen as the platforms for all radiobiology experiments in the 'BioQuaRT' project, because they allow targeting single cells (or compartments of a cell) with a predefined number of ionising particles and correlating the cell-by-cell induced damage with type and energy of the radiation and with the number of ions per cell. Within this project, a novel in situ protocol was developed for the analysis of the misrepaired and/or unrepaired chromosome damage induced by charged-particle irradiations at the Physikalisch-Technische Bundesanstalt (PTB) ion microbeam facility. Among the cytogenetic biomarkers to detect and estimate radiation-induced DNA damage in radiobiology, chromosomal aberrations and micronuclei were chosen. The characteristics of the PTB irradiation system required the design of a special in situ assay: specific irradiation dishes with a base made from a biofoil 25-µm thick and only 3000-4000 cells seeded and irradiated per dish. This method was developed on Chinese hamster ovary (CHO) cells, one of the most commonly used cell lines in radiobiology in vitro experiments. The present protocol allows the simultaneous scoring of chromosome aberrations and micronuclei on the same irradiated dish. Thanks to its versatility, this method could also be extended to other radiobiological applications besides the single-ion microbeam irradiations.

  11. 'BioQuaRT' project: design of a novel in situ protocol for the simultaneous visualisation of chromosomal aberrations and micronuclei after irradiation at microbeam facilities.

    PubMed

    Patrono, C; Monteiro Gil, O; Giesen, U; Langner, F; Pinto, M; Rabus, H; Testa, A

    2015-09-01

    The aim of the 'BioQuaRT' (Biologically weighted Quantities in RadioTherapy) project is to develop measurement techniques for characterising charged particle track structure on different length scales, and to correlate at the cellular level the track structure properties with the biological effects of radiation. This multi-scale approach will allow characterisation of the radiation qualities used in radiotherapy and the related biological effects. Charged-particle microbeam facilities were chosen as the platforms for all radiobiology experiments in the 'BioQuaRT' project, because they allow targeting single cells (or compartments of a cell) with a predefined number of ionising particles and correlating the cell-by-cell induced damage with type and energy of the radiation and with the number of ions per cell. Within this project, a novel in situ protocol was developed for the analysis of the misrepaired and/or unrepaired chromosome damage induced by charged-particle irradiations at the Physikalisch-Technische Bundesanstalt (PTB) ion microbeam facility. Among the cytogenetic biomarkers to detect and estimate radiation-induced DNA damage in radiobiology, chromosomal aberrations and micronuclei were chosen. The characteristics of the PTB irradiation system required the design of a special in situ assay: specific irradiation dishes with a base made from a biofoil 25-µm thick and only 3000-4000 cells seeded and irradiated per dish. This method was developed on Chinese hamster ovary (CHO) cells, one of the most commonly used cell lines in radiobiology in vitro experiments. The present protocol allows the simultaneous scoring of chromosome aberrations and micronuclei on the same irradiated dish. Thanks to its versatility, this method could also be extended to other radiobiological applications besides the single-ion microbeam irradiations. PMID:25877532

  12. Deactivation mechanisms for Pd/Al{sub 2}O{sub 3} acetylene hydrogenation catalysts

    SciTech Connect

    Hall, J.B.; Huggins, B.J.; Meyers, B.L.; Kaminsky, M.P.

    1994-12-31

    The selective hydrogenation of acetylenic impurities to ethylene is a crucial purification step in the production of olefins by steam cracking. This hydrogenation is done catalytically using a Pd/Al{sub 2}O{sub 3} catalyst in a fixed bed reactor. The designed lifetime of the catalyst in a front end acetylene converter is about 4 years. Accelerated catalyst deactivation and thermal runaways caused by loss in catalyst selectivity are common problems which plague acetylene converters. Such problems result in unscheduled shutdowns and increased costs to replace deactivated catalyst. This presentation outlines several deactivation mechanisms of the catalyst and discusses how they affect catalyst lifetime and performance. Catalyst characterization using electron microscopy and CO chemisorption provides information on how poisons deteriorate the catalyst and Pd particle size changes produced by use and regeneration. Thermal gravimetric analysis was also used to determine the extent of coke burn-off using less severe regeneration procedures.

  13. 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.

  14. 105-K Basin Material Design Basis Feed Description for Spent Nuclear Fuel (SNF) Project Facilities VOL 2 Sludge

    SciTech Connect

    PEARCE, K.L.

    2000-04-05

    Volume 2 provides estimated chemical and radionuclide inventories of sludge currently stored within the Hanford Site's 105-K Basin This volume also provides estimated chemical and radionuclide inventories for the sludge streams expected to be generated during Spent Nuclear Fuel (SNF) Project activities.

  15. Summary and evaluation of existing geological and geophysical data near prospective surface facilities in Midway Valley, Yucca Mountain Project, Nye County, Nevada; Yucca Mountain Site Characterization Project

    SciTech Connect

    Gibson, J.D.; Swan, F.H.; Wesling, J.R.; Bullard, T.F.; Perman, R.C.; Angell, M.M.; DiSilvestro, L.A.

    1992-01-01

    Midway Valley, located at the eastern base of the Yucca Mountain in southwestern Nevada, is the preferred location of the surface facilities for the potential high-level nuclear waste repository at Yucca Mountain. One goal in siting these surface facilities is to avoid faults that could produce relative displacements in excess of 5 cm in the foundations of the waste-handling buildings. This study reviews existing geologic and geophysical data that can be used to assess the potential for surface fault rupture within Midway Valley. Dominant tectonic features in Midway Valley are north-trending, westward-dipping normal faults along the margins of the valley: the Bow Ridge fault to the west and the Paintbrush Canyon fault to the east. Published estimates of average Quaternary slip rates for these faults are very low but the age of most recent displacement and the amount of displacement per event are largely unknown. Surface mapping and interpretive cross sections, based on limited drillhole and geophysical data, suggest that additional normal faults, including the postulated Midway Valley fault, may exist beneath the Quaternary/Tertiary fill within the valley. Existing data, however, are inadequate to determine the location, recency, and geometry of this faulting. To confidently assess the potential for significant Quaternary faulting in Midway Valley, additional data are needed that define the stratigraphy and structure of the strata beneath the valley, characterize the Quaternary soils and surfaces, and establish the age of faulting. The use of new and improved geophysical techniques, combined with a drilling program, offers the greatest potential for resolving subsurface structure in the valley. Mapping of surficial geologic units and logging of soil pits and trenches within these units must be completed, using accepted state-of-the-art practices supported by multiple quantitative numerical and relative age-dating techniques.

  16. The Optimizing Patient Transfers, Impacting Medical Quality, andImproving Symptoms:Transforming Institutional Care approach: preliminary data from the implementation of a Centers for Medicare and Medicaid Services nursing facility demonstration project.

    PubMed

    Unroe, Kathleen T; Nazir, Arif; Holtz, Laura R; Maurer, Helen; Miller, Ellen; Hickman, Susan E; La Mantia, Michael A; Bennett, Merih; Arling, Greg; Sachs, Greg A

    2015-01-01

    The Optimizing Patient Transfers, Impacting Medical Quality, and Improving Symptoms: Transforming Institutional Care (OPTIMISTIC) project aims to reduce avoidable hospitalizations of long-stay residents enrolled in 19 central Indiana nursing facilities. This clinical demonstration project, funded by the Centers for Medicare and Medicaid Services Innovations Center, places a registered nurse in each nursing facility to implement an evidence-based quality improvement program with clinical support from nurse practitioners. A description of the model is presented, and early implementation experiences during the first year of the project are reported. Important elements include better medical care through implementation of Interventions to Reduce Acute Care Transfers tools and chronic care management, enhanced transitional care, and better palliative care with a focus on systematic advance care planning. There were 4,035 long-stay residents in 19 facilities enrolled in OPTIMISTIC between February 2013 and January 2014. Root-cause analyses were performed for all 910 acute transfers of these long stay residents. Of these transfers, the project RN evaluated 29% as avoidable (57% were not avoidable and 15% were missing), and opportunities for quality improvement were identified in 54% of transfers. Lessons learned in early implementation included defining new clinical roles, integrating into nursing facility culture, managing competing facility priorities, communicating with multiple stakeholders, and developing a system for collecting and managing data. The success of the overall initiative will be measured primarily according to reduction in avoidable hospitalizations of long-stay nursing facility residents. PMID:25537789

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

    SciTech Connect

    BURKE, T.M.

    2005-04-13

    Deactivation activities are currently in progress at the Fast Flux Test Facility. These deactivation activities are intended to remove most hazardous materials and prepare the facility for final disposition. The two major hazards to be removed are the nuclear fuel and the alkali metal (most sodium) coolant. The fuel and coolant removal activities are proceeding well and are expected to complete in 2006. Plant systems are being shut down as allowed by completion of various fuel and coolant removal actions. A Decommissioning Environmental Impact Statement is in progress to evaluate a range of potential final disposition end states.

  18. Unilateral deactivation of macaque dorsolateral prefrontal cortex induces biases in stimulus selection.

    PubMed

    Johnston, Kevin; Lomber, Stephen G; Everling, Stefan

    2016-03-01

    Following unilateral brain injury, patients are often unable to detect a stimulus presented in the contralesional field when another is presented simultaneously ipsilesionally. This phenomenon has been referred to as extinction and has been conceptualized as a deficit in selective attention. Although most commonly observed following damage to posterior parietal areas, extinction has been observed following lesions of prefrontal cortex (PFC) in both humans and nonhuman primates. To date, most studies in nonhuman primates have examined lesions of multiple PFC subregions, including the frontal eye fields (FEF). Theoretical accounts of attentional disturbances from human patients, however, also implicate other PFC areas, including the middle frontal gyrus. Here, we investigated the effects of deactivating PFC areas anterior to the FEF on stimulus selection using a free-choice task. Macaque monkeys were presented with two peripheral stimuli appearing either simultaneously, or at varying stimulus onset asynchronies, and their performance was evaluated during unilateral cryogenic deactivation of part of dorsolateral prefrontal cortex or the cortex lining the caudal principal sulcus, the likely homologue of the human middle frontal gyrus. A decreased proportion of saccades was made to stimuli presented in the hemifield contralateral to the deactivated PFC. We also observed increases in reaction times to contralateral stimuli and decreases for stimuli presented in the hemifield ipsilateral to the deactivated hemisphere. In both cases, these results were greatest when both PFC subregions were deactivated. These findings demonstrate that selection biases result from PFC deactivation and support a role of dorsolateral prefrontal subregions anterior to FEF in stimulus selection. PMID:26792881

  19. Deactivation of 6-Aminocoumarin Intramolecular Charge Transfer Excited State through Hydrogen Bonding

    PubMed Central

    Krystkowiak, Ewa; Dobek, Krzysztof; Maciejewski, Andrzej

    2014-01-01

    This paper presents results of the spectral (absorption and emission) and photophysical study of 6-aminocoumarin (6AC) in various aprotic hydrogen-bond forming solvents. It was established that solvent polarity as well as hydrogen-bonding ability influence solute properties. The hydrogen-bonding interactions between S1-electronic excited solute and solvent molecules were found to facilitate the nonradiative deactivation processes. The energy-gap dependence on radiationless deactivation in aprotic solvents was found to be similar to that in protic solvents. PMID:25244014

  20. Beyond catalyst deactivation: cross-metathesis involving olefins containing N-heteroaromatics

    PubMed Central

    Lafaye, Kevin; Bosset, Cyril; Nicolas, Lionel

    2015-01-01

    Summary Alkenes containing N-heteroaromatics are known to be poor partners in cross-metathesis reactions, probably due to catalyst deactivation caused by the presence of a nitrogen atom. However, some examples of ring-closing and cross-metathesis involving alkenes that incorporate N-heteroaromatics can be found in the literature. In addition, recent mechanistic studies have focused on the rationalization of nitrogen-induced catalysts deactivation. The purpose of this mini-review is to give a brief overview of successful metathesis reactions involving olefins containing N-heteroaromatics in order to delineate some guidelines for the use of these challenging substrates in metathesis reactions. PMID:26664645

  1. Beyond catalyst deactivation: cross-metathesis involving olefins containing N-heteroaromatics.

    PubMed

    Lafaye, Kevin; Bosset, Cyril; Nicolas, Lionel; Guérinot, Amandine; Cossy, Janine

    2015-01-01

    Alkenes containing N-heteroaromatics are known to be poor partners in cross-metathesis reactions, probably due to catalyst deactivation caused by the presence of a nitrogen atom. However, some examples of ring-closing and cross-metathesis involving alkenes that incorporate N-heteroaromatics can be found in the literature. In addition, recent mechanistic studies have focused on the rationalization of nitrogen-induced catalysts deactivation. The purpose of this mini-review is to give a brief overview of successful metathesis reactions involving olefins containing N-heteroaromatics in order to delineate some guidelines for the use of these challenging substrates in metathesis reactions.

  2. Beyond catalyst deactivation: cross-metathesis involving olefins containing N-heteroaromatics.

    PubMed

    Lafaye, Kevin; Bosset, Cyril; Nicolas, Lionel; Guérinot, Amandine; Cossy, Janine

    2015-01-01

    Alkenes containing N-heteroaromatics are known to be poor partners in cross-metathesis reactions, probably due to catalyst deactivation caused by the presence of a nitrogen atom. However, some examples of ring-closing and cross-metathesis involving alkenes that incorporate N-heteroaromatics can be found in the literature. In addition, recent mechanistic studies have focused on the rationalization of nitrogen-induced catalysts deactivation. The purpose of this mini-review is to give a brief overview of successful metathesis reactions involving olefins containing N-heteroaromatics in order to delineate some guidelines for the use of these challenging substrates in metathesis reactions. PMID:26664645

  3. Evaluation of nuclear facility decommissioning projects: Summary status report: Three Mile Island Unit 2. Radioactive waste and laundry shipments

    SciTech Connect

    Doerge, D. H.; Haffner, D. R.

    1988-06-01

    This document summarizes information concerning radioactive waste and laundry shipments from the Three Mile Island Nuclear Station Unit 2 to radioactive waste disposal sites and to protective clothing decontamination facilities (laundries) since the loss of coolant accident experienced on March 28, 1979. Data were collected from radioactive shipment records, summarized, and placed in a computerized data information retrieval/manipulation system which permits extraction of specific information. This report covers the period of April 9, 1979 through April 19, 1987. Included in this report are: waste disposal site locations, dose rates, curie content, waste description, container type and number, volumes and weights. This information is presented in two major categories: protective clothing (laundry) and radioactive waste. Each of the waste shipment reports is in chronological order.

  4. National Ignition Facility Project Input for Assessment of Environmental Impacts of NIF for the Sitewide Environmental Impact Statement

    SciTech Connect

    Brereton, S

    2003-10-01

    This report provides the baseline data from which the environmental impacts of bounding NIF operations can be assessed. Included are operations in the NE Laser and Target Area Building (LTAB) and the Optics Assembly Building (OAB), (Buildings 581 and 681), and the Building 582 equipment building. The NIF is an experimental laser fusion facility undergoing construction and commissioning at Lawrence Livermore National Laboratory. The LTAB, the main experimental building of the NIF, is where laser-driven experiments will be conducted. The LTAB consists of two laser bays, two optical switchyards, a target bay, target diagnostics areas, capacitor bays, mechanical equipment areas, control rooms, and operational support areas. The LTAB provides an optically stable and clean environment and provides sufficient shielding against prompt radiation and residual radioactivity to meet the as low as reasonably achievable (ALARA) principle.

  5. Environmental assessment for the Strategic Petroleum Reserve Big Hill facility storage of commercial crude oil project, Jefferson County, Texas

    SciTech Connect

    1999-03-01

    The Big Hill SPR facility located in Jefferson County, Texas has been a permitted operating crude oil storage site since 1986 with benign environmental impacts. However, Congress has not authorized crude oil purchases for the SPR since 1990, and six storage caverns at Big Hill are underutilized with 70 million barrels of available storage capacity. On February 17, 1999, the Secretary of Energy offered the 70 million barrels of available storage at Big Hill for commercial use. Interested commercial users would enter into storage contracts with DOE, and DOE would receive crude oil in lieu of dollars as rental fees. The site could potentially began to receive commercial oil in May 1999. This Environmental Assessment identified environmental changes that potentially would affect water usage, power usage, and air emissions. However, as the assessment indicates, changes would not occur to a major degree affecting the environment and no long-term short-term, cumulative or irreversible impacts have been identified.

  6. Cost and Performance Report for the ASTD Reuse of Concrete Within DOE from D&D Projects

    SciTech Connect

    Kamboj, S.; Arnish, J.; Chen, S. Y.; Phillips, Ann Marie; Meservey, Richard Harlan; Tripp, Julia Lynn

    2000-09-01

    This cost and performance report describes the Accelerated Site Technology Deployment project that developed the Protocol for Development of Authorized Release Limits for Concrete at U.S. DOE Sites, which identifies the steps for obtaining approval to reuse concrete from Deactivation and Decommissioning of facilities. This protocol compares the risk and cost of various disposition paths for the concrete and follows the authorized release approach described in the DOE's draft handbook, Controlling Release for Reuse or Recycle of Property Containing Residual Radioactive Material. This approach provides for the development of authorized release limits through a series of prescribed steps before approval for release is granted. A case study was also completed on a previously decommissioned facility.

  7. DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

    SciTech Connect

    T. A. Lee

    2005-09-15

    The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

  8. Exemplary healthcare facilities.

    PubMed

    1992-01-01

    Symposium attendees had the opportunity to choose from 13 different tours designed to meet their diverse needs. Each tour consisted of one or more facilities grouped together to show innovative solutions to the problems in healthcare design today. Tours were of exemplary healthcare facilities throughout the Boston area, some of which were presented as case studies in the program. Facility types included medical centers with special services, ambulatory care centers, long term care facilities, pediatric hospitals, a school and center for the blind, a hospice, research and educational facilities, a community health center, an AIDS respite project, and a Ronald McDonald house. PMID:10183786

  9. Results of the combustion and emissions research project at the Vicon Incinerator Facility in Pittsfield, Massachusetts: Final report, Volume 3 (Appendices H-K)

    SciTech Connect

    Not Available

    1987-06-01

    The New York State Energy Research Development Authority (Energy Authority) contracted with Midwest Research Institute (MRI) to conduct a series of tests at the Municipal Solid Waste incineration facility operated by VICON Recovery Associates in Pittsfield, Massachusetts. The project was conducted in two phases. This final report presents the results of Phase II. Phase II was directed to the monitoring of combustion variables and to the sampling and analysis of polychlorinated dibenzo-p-dioxins, polychlorinated dibenzofurans, polychlorinated biphenyls, chlorobenzenes, chlorophenols, and polynuclear aromatic hydrocarbons in the combustion gases. Tests were conducted under several different incinerator operating conditions, including with different waste feeds, to identify any relationships between those compounds and the combustion variables and operating conditions. Dioxin/furan homolog distribution graphs and a summary of daily field testing logs are given, as well as MM5 calculations and analytical data and calculations for chlorine, moisture, and percent ash.

  10. Results of the combustion and emissions research project at the Vicon Incinerator Facility in Pittsfield, Massachusetts: Final report, Volume 4 (Appendices L-O)

    SciTech Connect

    Not Available

    1987-06-01

    The New York State Energy Research Development Authority (Energy Authority) contracted with Midwest Research Institute (MRI) to conduct a series of tests at the Municipal Solid Waste incineration facility operated by VICON Recovery Associates in Pittsfield, Massachusetts. The project was conducted in two phases. This final report presents the results of Phase 2. Phase 2 was directed to the monitoring of combustion variables and to the sampling and analysis of polychlorinated dibenzo-p-dioxins, polychlorinated dibenzofurans, polychlorinated biphenyls, chlorobenzenes, chlorophenols, and polynuclear aromatic hydrocarbons in the combustion gases. Tests were conducted under several different incinerator operating conditions, including with different waste feeds, to identify any relationships between those compounds and the combustion variables and operating conditions. Time frequency plots for selected operating parameters are given as well as statistical percent analysis for stack gas and combustion parameters. Statistical procedures and Phase 1 data are summarized.

  11. Results of the combustion and emissions research project at the Vicon Incinerator Facility in Pittsfield, Massachusetts: Final report, Volume 2 (Appendices A-G)

    SciTech Connect

    Not Available

    1987-06-01

    The New York State Energy Research Development Authority (Energy Authority) contracted with Midwest Research Institute (MRI) to conduct a series of tests at the Municipal Solid Waste incineration facility operated by VICON Recovery Associates in Pittsfield, Massachusetts. The project was conducted in two phases. This final report presents the results of Phase 2. Phase 2 was directed to the monitoring of combustion variables and to the sampling and analysis of polychlorinated dibenzo-p-dioxins, polychlorinated dibenzofurans, polychlorinated biphenyls, chlorobenzenes, chlorophenols, and polynuclear aromatic hydrocarbons in the combustion gases. Tests were conducted under several different incinerator operating conditions, including with different waste feeds, to identify any relationships between those compounds and the combustion variables and operating conditions. Compilations of the analytical chemical analyzers for semivolatile chemical emissions are tabulated, and quality assurance results are given.

  12. Geotechnical characterization of the North Ramp of the Exploratory Studies Facility: Yucca Mountain Site Characterization Project. Volume 2, NRG corehole data appendices

    SciTech Connect

    Brechtel, C.E.; Lin, Ming; Martin, E.; Kessel, D.S.

    1995-05-01

    This report presents the results of the 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 excavations of the Exploratory Studies Facility (ESF) North Ramp. The information in this report was developed to support the design of the ESF North Ramp. The ESF 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 potential to locate the national high-level nuclear waste repository on land within and adjacent to the Nevada Test Site (NTS), 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 to Provide Soil and Rock Properties. This is volume 2 which contains NRG Corehole Data for each of the NRG Holes.

  13. Resource conservation and recovery act ground-water monitoring projects for Hanford facilities: Progress report, January 1--March 31, 1989

    SciTech Connect

    Smith, R.M.; Bates, D.J.; Lundgren, R.E.

    1989-06-01

    This document describes the progress of 13 Hanford Site ground-water monitoring projects for the period January 1 to March 31, 1989. The work described in this document is conducted by the Pacific Northwest Laboratory under the management of Westinghouse Hanford Company for the US Department of Energy. Concentrations of ground-water constituents are compared to federal drinking water standards throughout this document for reference purposes. All drinking water supplied from the sampled aquifer meets regulatory standards for drinking water quality. 32 refs., 30 figs., 103 tabs.

  14. Failure of hippocampal deactivation during loss events in treatment-resistant depression.

    PubMed

    Johnston, Blair A; Tolomeo, Serenella; Gradin, Victoria; Christmas, David; Matthews, Keith; Steele, J Douglas

    2015-09-01

    Major depressive disorder is characterized by anhedonia, cognitive biases, ruminations, hopelessness and increased anxiety. Blunted responses to rewards have been reported in a number of recent neuroimaging and behavioural studies of major depressive disorder. In contrast, neural responses to aversive events remain an under-studied area. While selective serotonergic reuptake inhibitors are often effective in treating major depressive disorder, their mechanism of action remains unclear. Following a series of animal model investigations of depressive illness and serotonergic function, Deakin and Graeff predicted that brain activity in patients with major depressive disorder is associated with an overactive dorsal raphe nucleus with overactive projections to the amygdala, periaqueductal grey and striatum, and an underactive median raphe nucleus with underactive projections to the hippocampus. Here we describe an instrumental loss-avoidance and win-gain reinforcement learning functional magnetic resonance imaging study with 40 patients with highly treatment-resistant major depressive disorder and never-depressed controls. The dorsal raphe nucleus/ periaqueductal grey region of the midbrain and hippocampus were found to be overactive in major depressive disorder during unsuccessful loss-avoidance although the median raphe nucleus was not found to be underactive. Hippocampal overactivity was due to a failure to deactivate during loss events in comparison to controls, and hippocampal over-activity correlated with depression severity, self-report 'hopelessness' and anxiety. Deakin and Graeff argued that the median raphe nucleus normally acts to inhibit consolidation of aversive memories via the hippocampus and this system is underactive in major depressive disorder, facilitating the development of ruminations, while the dorsal raphe nucleus system is engaged by distal cues predictive of threats and is overactive in major depressive disorder. During win events the striatum

  15. Project W-026, Waste Receiving and Processing (WRAP) Facility Module 1: Maximum possible fire loss (MPFL) decontamination and cleanup estimates. Revision 1

    SciTech Connect

    Hinkle, A.W.; Jacobsen, P.H.; Lucas, D.R.

    1994-06-30

    Project W-026, Waste Receiving and Processing (WRAP) Facility Module 1, a 1991 Line Item, is planned for completion and start of operations in the spring of 1997. WRAP Module 1 will have the capability to characterize and repackage newly generated, retrieved and stored transuranic (TRU), TRU mixed, and suspect TRU waste for shipment to the Waste isolation Pilot Plant (WIPP). In addition, the WRAP Facility Module 1 will have the capability to characterize low-level mixed waste for treatment in WRAP Module 2A. This report documents the assumptions and cost estimates for decontamination and clean-up of a maximum possible fire loss (MPFL) as defined by DOE Order 5480.7A, FIRE PROTECTION. The Order defines MPFL as the value of property, excluding land, within a fire area, unless a fire hazards analysis demonstrates a lesser (or greater) loss potential. This assumes failure of both automatic fire suppression systems and manual fire fighting efforts. Estimates were developed for demolition, disposal, decontamination, and rebuilding. Total costs were estimated to be approximately $98M.

  16. A dedicated 26-m SETI sky survey instrument facility: A feasibility study

    NASA Technical Reports Server (NTRS)

    Berman, A. L.; Shaffer, R. D.

    1981-01-01

    The feasibility of converting a deactivated GSTDN 26 m facility into a dedicated SETI Instrument Facility is examined. Additional benefits that would accrue from the proposed utilization of these facilities are the capability for remote and control the Deep Space Communications Complex (DSCC) Signal Processing Center, combined with a reduction in ground-induced radio frequency interference due to the physical distance to the other DSCC front end areas and the Signal Processing Center.

  17. Object category classification of fMRI data using support vector machine combined with deactivation voxel selection

    NASA Astrophysics Data System (ADS)

    Yan, Caifeng; Song, Sutao; Li, Yao; Guo, Xiaojuan

    2012-03-01

    Support Vector Machine (SVM) is an accurate pattern recognition method which has been widely used in functional MRI (fMRI) data classification. Voxel selection is a very important part in classification. In general, voxel selection is based on brain regions associated with activation caused by different experiment conditions or stimulations. However, negative blood oxygenation level-dependent responses (deactivation) which have also been found in humans or animals contribute to the classification of different cognitive tasks. Different from traditional studies which focused merely on the activation voxel selection methods, our aim is to investigate the deactivation voxel selection methods in the classification of fMRI data using SVM. In this study, three different voxel selection methods (deactivation, activation, the combination of deactivation and activation) are applied to decide which voxel is included in SVM classifier with linear kernel in classifying 4-category objects on fMRI data. The average accuracies of deactivation classification were 73.36%(house vs. face), 60.34%(house vs. car), 60.94%(house vs. cat), 71.43%(face vs. car), 63.17%(face vs. cat) and 61.61%(car vs. cat). The classification results of deactivation were significantly above the chance level which implies the deactivation is informative. The accuracies of combination of activation and deactivation method were close to that of activation method, and it was even better for some representative subjects. These results suggest deactivation provides useful information in the object category classification on fMRI data and the method of voxel selection based on both activation and deactivation will be a significant method in classification in the future.

  18. A One Year Study of Mode Deactivation Therapy: Adolescent Residential Patients with Conduct and Personality Disorders

    ERIC Educational Resources Information Center

    Murphy, Christopher J.; Siv, Alexander M.

    2007-01-01

    This case study is to evaluate the effectiveness of Mode Deactivation Therapy (MDT) implementation in a child and adolescent residential treatment unit and provide preliminary effectiveness data on MDT versus treatment as usual (TAU). This case study compared the efficacy of two treatment methodologies for adolescent males in residential treatment…

  19. Family Mode Deactivation Therapy as a Manualized Cognitive Behavioral Therapy Treatment

    ERIC Educational Resources Information Center

    Apsche, Jack A.; Bass, Christopher K.; Houston, Marsha-Ann

    2008-01-01

    This article examines the effectiveness of Mode Deactivation Family Therapy (MDT) in an outpatient setting as compared to Treatment as Usual (TAU). MDT is an evidence-based psychotherapy and has been shown to be effective treating adolescents with a variety of problems involving emotional disorder, physical and sexual aggression, as well as…

  20. A One Year Study of Mode Deactivation Therapy: Adolescent Residential Patients with Conduct and Personality Disorders

    ERIC Educational Resources Information Center

    Murphy, Christopher J.; Siv, Alexander M.

    2011-01-01

    This case study is to evaluate the effectiveness of Mode Deactivation Therapy (MDT) implementation in a child and adolescent residential treatment unit and provide preliminary effectiveness data on MDT versus treatment as usual (TAU). This case study compared the efficacy of two treatment methodologies for adolescent males in residential treatment…