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Sample records for technical baseline summary

  1. FAIR - Baseline technical report. Executive summary

    International Nuclear Information System (INIS)

    Gutbrod, H.H.; Augustin, I.; Eickhoff, H.; Gross, K.D.; Henning, W.F.; Kraemer, D.; Walter, G.

    2006-09-01

    This document presents the Executive Summary, the first of six volumes comprising the 2006 Baseline Technical Report (BTR) for the international FAIR project (Facility for Antiproton and Ion Research). The BTR provides the technical description, cost, schedule, and assessments of risk for the proposed new facility. The purpose of the BTR is to provide a reliable basis for the construction, commissioning and operation of FAIR. The BTR is one of the central documents requested by the FAIR International Steering Committee (ISC) and its working groups, in order to prepare the legal process and the decisions on the construction and operation of FAIR in an international framework. It provides the technical basis for legal contracts on contributions to be made by, so far, 13 countries within the international FAIR Consortium. The BTR begins with this extended Executive Summary as Volume 1, which is also intended for use as a stand-alone document. The Executive Summary provides brief summaries of the accelerator facilities, the scientific programs and experimental stations, civil construction and safety, and of the workproject structure, costs and schedule. (orig.)

  2. Tank waste remediation system technical baseline summary description

    International Nuclear Information System (INIS)

    Raymond, R.E.

    1998-01-01

    This document is one of the tools used to develop and control the mission work as depicted in the included figure. This Technical Baseline Summary Description document is the top-level tool for management of the Technical Baseline for waste storage operations

  3. K Basin Fuel Characterization Program Technical Baseline Summary

    International Nuclear Information System (INIS)

    SUYAMA, R.M.

    1999-01-01

    This document provides a summary of the systematic process used by the SNF Project to characterize K-Basin spent fuel, and to develop and apply the appropriate conservative safety margins to the resulting parameters for technical designs and safety analyses

  4. Technical Baseline Summary Description for the Tank Farm Contractor

    International Nuclear Information System (INIS)

    TEDESCHI, A.R.

    2000-01-01

    This document is a revision of the document titled above, summarizing the technical baseline of the Tank Farm Contractor. It is one of several documents prepared by CH2M HILL Hanford Group, Inc. to support the U.S. Department of Energy Office of River Protection Tank Waste Retrieval and Disposal Mission at Hanford

  5. Tank Waste Remediation System retrieval and disposal mission technical baseline summary description

    International Nuclear Information System (INIS)

    McLaughlin, T.J.

    1998-01-01

    This document is prepared in order to support the US Department of Energy's evaluation of readiness-to-proceed for the Waste Retrieval and Disposal Mission at the Hanford Site. The Waste Retrieval and Disposal Mission is one of three primary missions under the Tank Waste Remediation System (TWRS) Project. The other two include programs to characterize tank waste and to provide for safe storage of the waste while it awaits treatment and disposal. The Waste Retrieval and Disposal Mission includes the programs necessary to support tank waste retrieval, wastefeed, delivery, storage and disposal of immobilized waste, and closure of tank farms. This mission will enable the tank farms to be closed and turned over for final remediation. The Technical Baseline is defined as the set of science and engineering, equipment, facilities, materials, qualified staff, and enabling documentation needed to start up and complete the mission objectives. The primary purposes of this document are (1) to identify the important technical information and factors that should be used by contributors to the mission and (2) to serve as a basis for configuration management of the technical information and factors

  6. TWRS technical baseline database manager definition document

    International Nuclear Information System (INIS)

    Acree, C.D.

    1997-01-01

    This document serves as a guide for using the TWRS Technical Baseline Database Management Systems Engineering (SE) support tool in performing SE activities for the Tank Waste Remediation System (TWRS). This document will provide a consistent interpretation of the relationships between the TWRS Technical Baseline Database Management software and the present TWRS SE practices. The Database Manager currently utilized is the RDD-1000 System manufactured by the Ascent Logic Corporation. In other documents, the term RDD-1000 may be used interchangeably with TWRS Technical Baseline Database Manager

  7. Hanford Site technical baseline database. Revision 1

    International Nuclear Information System (INIS)

    Porter, P.E.

    1995-01-01

    This report lists the Hanford specific files (Table 1) that make up the Hanford Site Technical Baseline Database. Table 2 includes the delta files that delineate the differences between this revision and revision 0 of the Hanford Site Technical Baseline Database. This information is being managed and maintained on the Hanford RDD-100 System, which uses the capabilities of RDD-100, a systems engineering software system of Ascent Logic Corporation (ALC). This revision of the Hanford Site Technical Baseline Database uses RDD-100 version 3.0.2.2 (see Table 3). Directories reflect those controlled by the Hanford RDD-100 System Administrator. Table 4 provides information regarding the platform. A cassette tape containing the Hanford Site Technical Baseline Database is available

  8. Summary Report for the Technical Interchange Meeting on Development of Baseline Material Properties and Design Guidelines for In-Space Manufacturing Activities

    Science.gov (United States)

    Prater, T. J.; Bean, Q. A.; Werkheiser, N. J.; Johnston, M. M.; Ordonez, E. A.; Ledbetter, F. E.; Risdon, D. L.; Stockman, T. J.; Sandridge, S. K. R.; Nelson, G. M.

    2016-01-01

    NASA Marshall Space Flight Center (MSFC) and the Agency as a whole are currently engaged in a number of in-space manufacturing (ISM) activities that have the potential to reduce launch costs, enhance crew safety, and provide the capabilities needed to undertake long-duration spaceflight. The recent 3D Printing in Zero-G experiment conducted on board the International Space Station (ISS) demonstrated that parts of acrylonitrile butadiene styrene (ABS) plastic can be manufactured in microgravity using fused deposition modeling (FDM). This project represents the beginning of the development of a capability that is critical to future NASA missions. Current and future ISM activities will require the development of baseline material properties to facilitate design, analysis, and certification of materials manufactured using in-space techniques. The purpose of this technical interchange meeting (TIM) was to bring together MSFC practitioners and experts in materials characterization and development of baseline material properties for emerging technologies to advise the ISM team as we progress toward the development of material design values, standards, and acceptance criteria for materials manufactured in space. The overall objective of the TIM was to leverage MSFC's shared experiences and collective knowledge in advanced manufacturing and materials development to construct a path forward for the establishment of baseline material properties, standards development, and certification activities related to ISM. Participants were asked to help identify research and development activities that will (1) accelerate acceptance and adoption of ISM techniques among the aerospace design community; (2) benefit future NASA programs, commercial technology developments, and national needs; and (3) provide opportunities and avenues for further collaboration.

  9. Information architecture. Volume 2, Part 1: Baseline analysis summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

    The Department of Energy (DOE) Information Architecture, Volume 2, Baseline Analysis, is a collaborative and logical next-step effort in the processes required to produce a Departmentwide information architecture. The baseline analysis serves a diverse audience of program management and technical personnel and provides an organized way to examine the Department`s existing or de facto information architecture. A companion document to Volume 1, The Foundations, it furnishes the rationale for establishing a Departmentwide information architecture. This volume, consisting of the Baseline Analysis Summary (part 1), Baseline Analysis (part 2), and Reference Data (part 3), is of interest to readers who wish to understand how the Department`s current information architecture technologies are employed. The analysis identifies how and where current technologies support business areas, programs, sites, and corporate systems.

  10. 100-D Area technical baseline report

    International Nuclear Information System (INIS)

    Carpenter, R.W.

    1993-01-01

    This document is prepared in support of the 100 Area Environmental Restoration activity at the US Department of Energy's Hanford Site near Richland, Washington. It provides a technical baseline of waste sites located at the 100-D Area. The report is based on an environmental investigation undertaken by the Westinghouse Hanford Company (WHC) History Office in support of the Environmental Restoration Engineering Function and on review and evaluation of numerous Hanford Site current and historical reports, drawings, and photographs, supplemented by site inspections and employee interviews. No intrusive field investigation or sampling was conducted. All Hanford coordinate locations are approximate locations taken from several different maps and drawings of the 100-D Area. Every effort was made to derive coordinate locations for the center of each facility or waste site, except where noted, using standard measuring devices. Units of measure are shown as they appear in reference documents. The 100-D Area is made up of three operable units: 100-DR-1, 100-DR-2, and 100-DR-3. All three are addressed in this report. These operable units include liquid and solid waste disposal sites in the vicinity of, and related to, the 100-D and 100-DR Reactors. A fourth operable unit, 100-HR-3, is concerned with groundwater and is not addressed here. This report describes waste sites which include cribs, trenches, pits, french drains, retention basins, solid waste burial grounds, septic tanks, and drain fields. Each waste site is described separately and photographs are provided where available. A complete list of photographs can be found in Appendix A. A comprehensive environmental summary is not provided here but may be found in Hanford Site National Environmental Policy Act Characterization (Cushing 1988), which describes the geology and soils, meteorology, hydrology, land use, population, and air quality of the area

  11. Waste management project technical baseline description

    International Nuclear Information System (INIS)

    Sederburg, J.P.

    1997-01-01

    A systems engineering approach has been taken to describe the technical baseline under which the Waste Management Project is currently operating. The document contains a mission analysis, function analysis, requirement analysis, interface definitions, alternative analysis, system definition, documentation requirements, implementation definitions, and discussion of uncertainties facing the Project

  12. Solid Waste Program technical baseline description

    Energy Technology Data Exchange (ETDEWEB)

    Carlson, A.B.

    1994-07-01

    The system engineering approach has been taken to describe the technical baseline under which the Solid Waste Program is currently operating. The document contains a mission analysis, function analysis, system definition, documentation requirements, facility and project bases, and uncertainties facing the program.

  13. INDOT Technical Training Plan : [Technical Summary

    Science.gov (United States)

    2012-01-01

    A wide range of job classifications, increasing technical : performance expectations, licensing and certification requirements, : budget restrictions and frequent department : reorganization has made technical training of employees : more difficult, ...

  14. Summary of Sandia Laboratories technical capabilities

    International Nuclear Information System (INIS)

    1977-05-01

    The technical capabilities of Sandia Laboratories are detailed in a series of companion reports. In this summary the use of the capabilities in technical programs is outlined and the capabilities are summarized. 25 figures, 3 tables

  15. Summary of Technical Sessions - Summary and Recommendations

    International Nuclear Information System (INIS)

    2013-01-01

    Technical Session 1 - Development achievements of BEPU methods and State of the Art: The objective of this session was to present the different approaches dealing with Best Estimate codes and uncertainties evaluations. Existing methods were summarized and different papers were focused on specific methods stressing their bases, peculiarities, advantages and limitations. As a result of the session a picture of the current State of the Art was obtained. The session comprised six papers. Technical Session 2 - International comparative activities: This session had as a main objective to review the activities launched in the past and present from the NEA in connection with BEPU methods, with focus on the applicability of conclusions derived from former benchmarks like UMS, the main outcomes of the recently finished BEMUSE project, and the objectives and relevance of UAM and PREMIUM projects. The session comprised four papers. Technical Session 3 - Applications: Licensing, safety analysis support, regulatory body views and industry activities: This session focused on the application of current methods in safety analyses. Contributions from industry, technical safety organizations and regulatory bodies were provided. As a result, a view of the penetration of BEPU methods in current safety analyses was obtained, as well as an indication of the evolution in the near future. Elements such as licensing practices, assessment process, etc. were considered. The session comprised nine papers. Technical Session 4. BEPU methods extension to new fields The session addressed the extension of BEPU methods beyond their current use. By now such methods are mainly applied to classic deterministic environment but it is believed that their benefits could be extended to other fields. Seven papers were presented in the session dealing with subjects that fit in the objectives established in the workshop programme. The papers cover areas like: extension to CFD, quantification of global safety

  16. USACE AIS Transmit Technical Support Summary Report

    Science.gov (United States)

    2014-09-01

    the TAG block for the correct transmitters, and then send to the USACE AIS network. B. Outbound openings in the USCG firewall for the USCG Message...USACE AIS Transmit Technical Support Summary Report Distribution Statement A: Approved for public release; distribution is unlimited...September 2014 Report No. CD-D-09-15 USACE AIS Transmit Technical Support Summary Report ii UNCLAS//Public | CG-926 RDC | I. Gonin et al. Public

  17. Design mentoring tool : [technical summary].

    Science.gov (United States)

    2011-01-01

    In 2004 a design engineer on-line mentoring tool was developed and implemented The purpose of the tool was to assist senior engineers mentoring new engineers to the INDOT design process and improve their technical competency. This approach saves seni...

  18. 200-BP-5 operable unit Technical Baseline report

    International Nuclear Information System (INIS)

    Jacques, I.D.; Kent, S.K.

    1991-10-01

    This report supports development of a remedial investigation/feasibility study work plan for the 200-BP-5 operable unit. The report summarizes baseline information for waste sites and unplanned release sites located in the 200-BP-5 operable unit. The sites were investigated by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (Westinghouse Hanford). The investigation consisted of review and evaluation of current and historical Hanford Site reports, drawings, and photographs, and was supplemented with recent inspections of the Hanford Site and employee interviews. No field investigations or sampling were conducted

  19. S Plant Aggregate Area Management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    This document is prepared in support of an Aggregate Area Management Study of S Plant, 200 West Area, at the US Department of Energy's (DOE) Hanford Site near Richland, Washington. It provides a technical baseline of the aggregate area and the results from an environmental investigation undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (WHC). This document is based on review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. This report describes the REDOX facility and its waste sites, including cribs, french drains, septic tanks and drain fields, trenches, catch tanks, settling tanks, diversion boxes, underground tank farms designed for high-level liquid wastes, and the lines and encasements that connect them

  20. Technical baseline description for in situ vitrification laboratory test equipment

    International Nuclear Information System (INIS)

    Beard, K.V.; Bonnenberg, R.W.; Watson, L.R.

    1991-09-01

    IN situ vitrification (ISV) has been identified as possible waste treatment technology. ISV was developed by Pacific Northwest Laboratory (PNL), Richland, Washington, as a thermal treatment process to treat contaminated soils in place. The process, which electrically melts and dissolves soils and associated inorganic materials, simultaneously destroys and/or removes organic contaminants while incorporating inorganic contaminants into a stable, glass-like residual product. This Technical Baseline Description has been prepared to provide high level descriptions of the design of the Laboratory Test model, including all design modifications and safety improvements made to data. Furthermore, the Technical Baseline Description provides a basic overview of the interface documents for configuration management, program management interfaces, safety, quality, and security requirements. 8 figs

  1. Mixed Waste Focus Area integrated technical baseline report, Phase 1: Volume 1

    International Nuclear Information System (INIS)

    1996-01-01

    The Department of Energy (DOE) established the Mixed Waste Characterization, Treatment, and Disposal Focus Area (MWFA) to develop and facilitate implementation of technologies required to meet the Department's commitments for treatment of mixed low-level and transuranic wastes. The mission of the MWFA is to provide acceptable treatment systems, developed in partnership with users and with participation of stakeholders, tribal governments, and regulators, that are capable of treating DOE's mixed waste. These treatment systems include all necessary steps such as characterization, pretreatment, and disposal. To accomplish this mission, a technical baseline is being established that forms the basis for determining which technology development activities will be supported by the MWFA. The technical baseline is the prioritized list of deficiencies, and the resulting technology development activities needed to overcome these deficiencies. This document presents Phase I of the technical baseline development process, which resulted in the prioritized list of deficiencies that the MWFA will address. A summary of the data and the assumptions upon which this work was based is included, as well as information concerning the DOE Office of Environmental Management (EM) mixed waste technology development needs. The next phase in the technical baseline development process, Phase II, will result in the identification of technology development activities that will be conducted through the MWFA to resolve the identified deficiencies

  2. 200-UP-2 Operable Unit technical baseline report

    International Nuclear Information System (INIS)

    Deford, D.H.

    1991-02-01

    This report is prepared in support of the development of a Remedial Investigation/Feasibility Study (RI/FS) Work Plan for the 200-UP-2 Operable Unit by EBASCO Environmental, Incorporated. It provides a technical baseline of the 200-UP-2 Operable Unit and results from an environmental investigation undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (Westinghouse Hanford). The 200-UP-2 Operable Unit Technical Baseline Report is based on review and evaluation of numerous Hanford Site current and historical reports, Hanford Site drawings and photographs and is supplemented with Hanford Site inspections and employee interviews. No field investigations or sampling were conducted. Each waste site in the 200-UP-2 Operable Unit is described separately. Close relationships between waste units, such as overflow from one to another, are also discussed. The 200-UP-2 Operable Unit consists of liquid-waste disposal sites in the vicinity of, and related to, U Plant operations in the 200 West Area of the Hanford Site. The ''U Plant'' refers to the 221-U Process Canyon Building, a chemical separations facility constructed during World War 2. It also includes the Uranium Oxide (UO 3 ) Plant, which was constructed at the same time and, like the 221-U Process Canyon Building, was later converted for other missions. Waste sites in the 200-UP-2 Operable Unit are associated with the U Plant Uranium Metal Recovery Program mission that occurred between 1952 and 1958 and the UO 3 Plant's ongoing uranium oxide mission and include one or more cribs, reverse wells, french drains, septic tanks and drain fields, trenches, catch tanks, settling tanks, diversion boxes, waste vaults, and the lines and encasements that connect them. 11 refs., 1 tab

  3. Z plant aggregate area management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    This document was prepared in support of the development of a Aggregate Area Management Study of Z Plant, 200 West Area, at the US Department of Energy (DOE) Hanford Site near Richland, Washington. It provides a technical description and operational history of the aggregate area and results from an environmental investigation undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (WHC) which is currently the Waste Site and Facility Research Office, Natural Resources, Bechtel Hanford, Inc. (BHI). It is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. No intrusive field investigations or sampling were conducted in support of this report

  4. Spent Nuclear Fuel Project technical baseline document. Fiscal year 1995: Volume 1, Baseline description

    International Nuclear Information System (INIS)

    Womack, J.C.; Cramond, R.; Paedon, R.J.

    1995-01-01

    This document is a revision to WHC-SD-SNF-SD-002, and is issued to support the individual projects that make up the Spent Nuclear Fuel Project in the lower-tier functions, requirements, interfaces, and technical baseline items. It presents results of engineering analyses since Sept. 1994. The mission of the SNFP on the Hanford site is to provide safety, economic, environmentally sound management of Hanford SNF in a manner that stages it to final disposition. This particularly involves K Basin fuel, although other SNF is involved also

  5. U Plant Aggregate Area Management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    This document was prepared in support of an Aggregate Area Management Study of U Plant. It provides a technical baseline of the aggregate area and results from an environmental investigation that was undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (WHC), which is currently the Waste Site and Facility Research Office, Natural Resources, Bechtel Hanford, Inc. (BHI). It is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. U Plant refers to the 221-U Process Canyon Building, a chemical separation facility constructed during World War II. It also includes the Uranium Oxide (UO 3 ) Plant constructed at the same time as 221-U as an adjunct to the original plutonium separation process but which, like 221-U, was converted for other missions. Waste sites are associated primarily with U Plant's 1952 through 1958 Uranium Metal Recovery Program mission and the U0 3 Plant's ongoing U0 3 mission. Waste sites include cribs, reverse wells, french drains, septic tanks and drain fields, trenches, catch tanks, settling tanks, diversion boxes, a waste vault, and the lines and encasements that connect them. It also includes the U Pond and its feed ditches and an underground tank farm designed for high-level liquid wastes

  6. PUREX Plant aggregate area management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    The PUREX aggregate area is made up of six operable units; 200-PO-1 through 200-PO-6 and consists of liquid and solid waste disposal sites in the vicinity of, and related to, PUREX Plant operations. This report describes PUREX and its waste sites, including cribs, french drains, septic tanks and drain fields, trenches and ditches, ponds, catch tanks, settling tanks, diversion boxes, underground tank farms, and the lines and encasements that connect them. Each waste site in the aggregate area is described separately. Close relationships between waste units, such as overflow from one to another, are also discussed. This document provides a technical baseline of the aggregate area and results from an environmental investigation. This document is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. No intrusive field investigations or sampling were conducted

  7. FHWA vehicle crash analysis conference proceedings : technical summary

    Science.gov (United States)

    1997-04-01

    This technical summary announces the publication of conference proceedings as a Federal Highway Administration (FHWA) report (FHWA-RD-96-212) of the same title. The report represents a compilation of seven research papers presented at The FHWA Veh...

  8. INC93: international nuclear congress. Technical sessions summaries

    International Nuclear Information System (INIS)

    Boulton, J.

    1993-01-01

    The conference dealt mainly with safety, environmental and human aspects of nuclear energy, including waste management. This volume consists of summaries of the technical sessions contained in Volumes 2 and 3. The individual papers have also been abstracted separately for INIS, with the summaries abridged

  9. INC93: international nuclear congress. Technical sessions summaries

    Energy Technology Data Exchange (ETDEWEB)

    Boulton, J

    1994-12-31

    The conference dealt mainly with safety, environmental and human aspects of nuclear energy, including waste management. This volume consists of summaries of the technical sessions contained in Volumes 2 and 3. The individual papers have also been abstracted separately for INIS, with the summaries abridged.

  10. B Plant aggregate area management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    The B aggregate area is made up of 13 operable units; 200-BP 1 through 200-BP 1 1, 200-IU-6, and 200-SS-1 that consist of liquid and solid waste disposal sites in the vicinity of, and related to, B Plant operations. This report describes B Plant and its waste sites, including cribs, french drains, septic tanks and drain fields, trenches and ditches, ponds, catch tanks, settling tanks, diversion boxes, underground tank farms designed for high-level liquid wastes, and the lines and encasements that connect them. Each waste site in the aggregate area is described separately. Close relationships between waste units, such as overflow from one to another, are also discussed. This document provides a technical baseline of the aggregate area and results from an environmental investigation. This document is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. No intrusive field investigations or sampling were conducted

  11. Programmatic Baseline Summary for Phase 1 Privatization for the Tank Farm contractor

    Energy Technology Data Exchange (ETDEWEB)

    DIEDIKER, J.A.

    2000-04-22

    The document describes the systematic integrated baseline planning process and provides a summary of the Tank Farm Contractor scope, schedule and cost analysis developed in support of the Phase 1 privatization mission.

  12. Programmatic Baseline Summary for Phase 1 Privatization for the Tank Farm contractor

    International Nuclear Information System (INIS)

    DIEDIKER, J.A.

    2000-01-01

    The document describes the systematic integrated baseline planning process and provides a summary of the Tank Farm Contractor scope, schedule and cost analysis developed in support of the Phase 1 privatization mission

  13. Draft low level waste technical summary

    International Nuclear Information System (INIS)

    Powell, W.J.; Benar, C.J.; Certa, P.J.; Eiholzer, C.R.; Kruger, A.A.; Norman, E.C.; Mitchell, D.E.; Penwell, D.E.; Reidel, S.P.; Shade, J.W.

    1995-09-01

    The purpose of this document is to present an outline of the Hanford Site Low-Level Waste (LLW) disposal program, what it has accomplished, what is being done, and where the program is headed. This document may be used to provide background information to personnel new to the LLW management/disposal field and to those individuals needing more information or background on an area in LLW for which they are not familiar. This document should be appropriate for outside groups that may want to learn about the program without immediately becoming immersed in the details. This document is not a program or systems engineering baseline report, and personnel should refer to more current baseline documentation for critical information

  14. KBS Technical report 1-120 (1977-1978). Summaries

    International Nuclear Information System (INIS)

    1979-05-01

    The Swedish nuclear utilities started early in 1977 the KBS (nuclear fuel safety) project to study the high level waste problem and report on how and where a safe final storage could be arranged in Sweden. The docummentation produced by the project during 1977 and 1978 has been collected in a series of technical reports numbered from 1 to 120. The English summaries of the technical reports have been collected in this separate volume, No. 121. (G.B.)

  15. Biopower Technical Strategy Workshop Summary Report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2010-12-01

    Biopower is electricity produced from a wide range of biomass (organic materials found in wood, plants, agricultural waste and other materials). Biomass is a base load renewable energy source with high availability for electricity production. To explore opportunities for biopower in the United States, the U.S. Department of Energy (DOE), Office of Energy Efficiency and Renewable Energy Biomass Program conducted the Biopower Technical Strategy Workshop in Denver, Colorado, on December 2–3, 2009. This report summarizes the results of the workshop, which focused on challenges to the expanded use of biopower and the possible solutions, including technology research, development, and demonstration (RD&D) as well as policies and other market transformation mechanisms.

  16. Tank waste remediation system retrieval and disposal mission initial updated baseline summary

    International Nuclear Information System (INIS)

    Swita, W.R.

    1998-01-01

    This document provides a summary of the proposed Tank Waste Remediation System Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost) developed to demonstrate the Tank Waste Remediation System contractor's Readiness-to-Proceed in support of the Phase 1B mission

  17. Spent nuclear fuel technical baseline description, Fiscal Year 1996: Volume II, supporting data

    International Nuclear Information System (INIS)

    Womack, J.C.

    1995-11-01

    The Technical Baseline Description documents the Project-Level functions and requirements, along with associated enabling assumptions, issues, trade studies, interfaces, and products. It is a snapshot in time of the baseline at the beginning of September 1995. It supports the individual subprojects in the development of lower-tier functions, requirements, and specifications in FY 1996. It also supports the need for Hanford site planning to be based on an integrated Hanford site systems engineering technical baseline; and is traceable to that baseline. This document replaces and supercedes WHC-SD-SNF-SD-003

  18. US Department of Energy mixed waste characterization, treatment, and disposal focus area technical baseline development process

    International Nuclear Information System (INIS)

    Roach, J.A.; Gombert, D.

    1996-01-01

    The US Department of Energy (DOE) created the Mixed Waste Characterization, Treatment, and Disposal Focus Area (MWFA) to develop and facilitate implementation of technologies required to meet its commitments for treatment of mixed wastes under the Federal Facility Compliance Act (FFCA), and in accordance with the Land Disposal Restrictions (LDR) of the Resource Conservation and Recovery Act (RCRA). Mixed wastes include both mixed low-level waste (MLLW) and mixed transuranic (MTRU) waste. The goal of the MWFA is to develop mixed waste treatment systems to the point of implementation by the Environmental Management (EM) customer. To accomplish this goal, the MWFA is utilizing a three step process. First, the treatment system technology deficiencies were identified and categorized. Second, these identified needs were prioritized. This resulted in a list of technical deficiencies that will be used to develop a technical baseline. The third step, the Technical Baseline Development Process, is currently ongoing. When finalized, the technical baseline will integrate the requirements associated with the identified needs into the planned and ongoing environmental research and technology development activities supported by the MWFA. Completion of this three-step process will result in a comprehensive technology development program that addresses customer identified and prioritized needs. The MWFA technical baseline will be a cost-effective, technically-defensible tool for addressing and resolving DOE's mixed waste problems

  19. Summary report of technical meeting on neutron cross section covariances

    International Nuclear Information System (INIS)

    Trkov, A.; Smith, D.L.; Capote Noy, R.

    2011-01-01

    A summary is given of the Technical Meeting on Neutron Cross Section Covariances. The meeting goal was to assess covariance data needs and recommend appropriate methodologies to address those needs. Discussions on covariance data focused on three general topics: 1) Resonance and unresolved resonance regions; 2) Fast neutron region; and 3) Users' perspective: benchmarks' uncertainty and reactor dosimetry. A number of recommendations for further work were generated and the important work that remains to be done in the field of covariances was identified. (author)

  20. Preliminary technical data summary defense waste processing facility stage 2

    International Nuclear Information System (INIS)

    1980-12-01

    This Preliminary Technical Data Summary presents the technical basis for design of Stage 2 of the Staged Defense Waste Processing Facility (DWPF). Process changes incorporated in the staged DWPF relative to the Alternative DWPF described in PTDS No. 3 (DPSTD-77-13-3) are the result of ongoing research and development and are aimed at reducing initial capital investment and developing a process to efficiently immobilize the radionuclides in Savannah River Plant (SRP) high-level liquid waste. The radionuclides in SRP waste are present in sludge that has settled to the bottom of waste storage tanks and in crystallized salt and salt solution (supernate). Stage 1 of the DWPF receives washed, aluminum dissolved sludge from the waste tank farms and immobilizes it in a borosilicate glass matrix. The supernate is retained in the waste tank farms until completion of Stage 2 of the DWPF at which time it is filtered and decontaminated by ion exchange in the Stage 2 facility. The decontaminated supernate is concentrated by evaporation and mixed with cement for burial. The radioactivity removed from the supernate is fixed in borosilicate glass along with the sludge. This document gives flowsheets, material and curie balances, material and curie balance bases, and other technical data for design of Stage 2 of the DWPF. Stage 1 technical data are presented in DPSTD-80-38

  1. 2011 PERFORMANCE ASSESSMENT COMMUNITY OF PRACTICE TECHNICAL EXCHANGE - SUMMARY

    Energy Technology Data Exchange (ETDEWEB)

    Seitz, R.

    2011-12-30

    The Performance Assessment Community of Practice (PA CoP) was developed in 2008 to improve consistency and quality in the preparation of performance assessments (PAs) and risk assessments across the Department of Energy (DOE) Complex. The term, PA, is used to represent all of these modeling applications in this report. The PA CoP goals are to foster the exchange of information among PA practitioners and to share lessons learned from PAs conducted for DOE, commercial disposal facilities, and international entities. Technical exchanges and workshops are a cornerstone of PA CoP activities. Previous technical exchanges have addressed Engineered Barriers (2009 - http://www.cresp.org/education/workshops/pacop/), the Advanced Simulation Capability for Environmental Management and the Cementitious Barriers Partnership (2010 - http://srnl.doe.gov/copexchange/links.htm). Each technical exchange also includes summary presentations regarding activities at DOE, the Nuclear Regulatory Commission (NRC) and other organizations (e.g., International Atomic Energy Agency (IAEA)) as well as a number of presentations from selected sites to provide insight and perspective from on-going modeling activities. Through the deployment of PA Assistance Teams, the PA CoP has also been engaged in the development of new PAs across the DOE Complex. As a way of improving consistency in the preparation of new PAs, the teams provide technical advice and share experiences, noteworthy practices, and lessons learned from previous Low-Level Waste Disposal Facility Federal Review Group (LFRG) reviews. Teams have provided support for PAs at Hanford, Idaho, Paducah and Portsmouth. The third annual PA CoP Technical Exchange was held on May 25-26, 2011 in Atlanta, GA. The PA CoP Steering Committee Meeting held its first meeting on May 24 prior to the Technical Exchange. Decision making using models and software quality assurance were the topical emphasis for the exchange. A new feature at the 2011 technical

  2. Estimating the cold war mortgage: The 1995 baseline environmental management report. Volume II: Site summaries

    International Nuclear Information System (INIS)

    1995-03-01

    This volume, Volume II presents the site data that was used to generate the Department of Energy's (DOE) initial Baseline Environmental Management Report (BEMR). The raw data was obtained by DOE field personnel from existing information sources and anticipated environmental management strategies for their sites and was tempered by general assumptions and guidance developed by DOE Headquarters personnel. This data was then integrated by DOE Headquarters personnel and modified to ensure that overall constraints such as funding and waste management capacity were addressed. The site summaries are presented by State and broken out by discrete activities and projects. The Volume I Glossary has been repeated to facilitate the reader's review of Volume II. The information presented in the site summaries represents the best data and assumptions available as of February 1, 1995. Assumptions that have not been mandated by formal agreement with appropriate regulators and other stakeholders do not constitute decisions by the Department nor do they supersede existing agreements. In addition, actions requiring decisions from external sources regarding unknowns such as future land use and funding/scheduling alternatives, as well as internal actions such as the Department's Strategic Realignment initiative, will alter the basis and general assumptions used to generate the results for this report. Consequently, the numbers presented in the site summaries do not represent outyear budget requests by the field installations

  3. Tank waste remediation system retrieval and disposal mission initial updated baseline summary

    International Nuclear Information System (INIS)

    Swita, W.R.

    1998-01-01

    This document provides a summary of the Tank Waste Remediation System (TWRS) Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost), developed to demonstrate Readiness-to-Proceed (RTP) in support of the TWRS Phase 1B mission. This Updated Baseline is the proposed TWRS plan to execute and measure the mission work scope. This document and other supporting data demonstrate that the TWRS Project Hanford Management Contract (PHMC) team is prepared to fully support Phase 1B by executing the following scope, schedule, and cost baseline activities: Deliver the specified initial low-activity waste (LAW) and high-level waste (HLW) feed batches in a consistent, safe, and reliable manner to support private contractors' operations starting in June 2002; Deliver specified subsequent LAW and HLW feed batches during Phase 1B in a consistent, safe, and reliable manner; Provide for the interim storage of immobilized HLW (IHLW) products and the disposal of immobilized LAW (ILAW) products generated by the private contractors; Provide for disposal of byproduct wastes generated by the private contractors; and Provide the infrastructure to support construction and operations of the private contractors' facilities

  4. Fiscal year 1996 U.S. Department of Energy, Richland Operations Office Site summary baseline

    International Nuclear Information System (INIS)

    Johndro-Collins, A.

    1995-10-01

    The technical baseline is a hierarchical description of the Hanford Site cleanup mission. This technical baseline does not address the science, technology, or economic transition missions. It begins with a definition of the existing conditions at the Hanford Site, provides a description of the end product or mission accomplishments at completion, presents a statement of the major requirements and constraints that must be observed during the performance of the mission, and provides a statement of the top-level strategic approach to accomplish the mission. Mission-level interfaces are also described. This information is further defined hierarchically in increasing levels of detail. This definition is composed of the following major elements: functions that are key task descriptions; requirements that are the measurable standards to which the functions must be performed; architectures which are specific engineering solutions or systems that perform the functions described earlier; and verification ensuring the system satisfies the requirements and fulfills the functions. The above information is supplemented with the following: interface data; risk analyses and watch lists; assumptions; and required analyses

  5. Mixed waste focus area integrated technical baseline report. Phase I, Volume 2: Revision 0

    International Nuclear Information System (INIS)

    1996-01-01

    This document (Volume 2) contains the Appendices A through J for the Mixed Waste Focus Area Integrated Technical Baseline Report Phase I for the Idaho National Engineering Laboratory. Included are: Waste Type Managers' Resumes, detailed information on wastewater, combustible organics, debris, unique waste, and inorganic homogeneous solids and soils, and waste data information. A detailed list of technology deficiencies and site needs identification is also provided

  6. NEXT-100 Technical Design Report (TDR). Executive Summary

    CERN Document Server

    ,

    2012-01-01

    In this Technical Design Report (TDR) we describe the NEXT-100 detector that will search for neutrinoless double beta decay in Xe-136. The document formalizes the ANGEL design presented in our Conceptual Design Report (CDR). The baseline detector is designed to hold a maximum of about 150 kg of xenon at 15 bar, or 100 kg at 10 bar. This option builds in the capability to increase the total isotope mass by 50% while keeping the operating pressure at a manageable level. The ANGEL design calls for an asymmetric TPC, with photomultipliers behind a transparent cathode and position-sensitive light pixels behind the anode. We have chosen the low background R11410-10 PMTs for energy and timing and Hamamatsu MPPCs (S10362-11-050P model) as tracking pixels. Each individual PMT will be isolated from the gas by an individual, pressure resistant enclosure and will be coupled to the sensitive volume through a sapphire window coated with terphenyl-butadiene (TPB) . MPPCs will be arranged in Dice Boards (DB) holding 64 senso...

  7. Airborne incidents : an econometric analysis of severity, December 31, 2014 : technical summary

    Science.gov (United States)

    2014-12-31

    This is a technical summary of the Airborne Incidents: An Econometric Analysis of Severity main report. : Airborne loss of separation incidents occur when an aircraft breaches the defined separation limit (vertical and/or horizontal) with anoth...

  8. Analysis of factors affecting baseline SF-36 Mental Component Summary in Adult Spinal Deformity and its impact on surgical outcomes.

    Science.gov (United States)

    Mmopelwa, Tiro; Ayhan, Selim; Yuksel, Selcen; Nabiyev, Vugar; Niyazi, Asli; Pellise, Ferran; Alanay, Ahmet; Sanchez Perez Grueso, Francisco Javier; Kleinstuck, Frank; Obeid, Ibrahim; Acaroglu, Emre

    2018-03-01

    To identify the factors that affect SF-36 mental component summary (MCS) in patients with adult spinal deformity (ASD) at the time of presentation, and to analyse the effect of SF-36 MCS on clinical outcomes in surgically treated patients. Prospectively collected data from a multicentric ASD database was analysed for baseline parameters. Then, the same database for surgically treated patients with a minimum of 1-year follow-up was analysed to see the effect of baseline SF-36 MCS on treatment results. A clinically useful SF-36 MCS was determined by ROC Curve analysis. A total of 229 patients with the baseline parameters were analysed. A strong correlation between SF-36 MCS and SRS-22, ODI, gender, and diagnosis were found (p baseline SF-36 MCS (p baseline SF-36 MCS in an ASD population are other HRQOL parameters such as SRS-22 and ODI as well as the baseline thoracic kyphosis and gender. This study has also demonstrated that baseline SF-36 MCS does not necessarily have any effect on the treatment results by surgery as assessed by SRS-22 or ODI. Level III, prognostic study. Copyright © 2018 Turkish Association of Orthopaedics and Traumatology. Production and hosting by Elsevier B.V. All rights reserved.

  9. The International Linear Collider Technical Design Report - Volume 3.II: Accelerator Baseline Design

    Energy Technology Data Exchange (ETDEWEB)

    Adolphsen, Chris [SLAC National Accelerator Lab., Menlo Park, CA (United States); et al.

    2013-06-26

    The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.

  10. The International Linear Collider Technical Design Report - Volume 3.II: Accelerator Baseline Design

    CERN Document Server

    Adolphsen, Chris; Barish, Barry; Buesser, Karsten; Burrows, Philip; Carwardine, John; Clark, Jeffrey; Durand, Helene Mainaud; Dugan, Gerry; Elsen, Eckhard; Enomoto, Atsushi; Foster, Brian; Fukuda, Shigeki; Gai, Wei; Gastal, Martin; Geng, Rongli; Ginsburg, Camille; Guiducci, Susanna; Harrison, Mike; Hayano, Hitoshi; Kershaw, Keith; Kubo, Kiyoshi; Kuchler, Victor; List, Benno; Liu, Wanming; Michizono, Shinichiro; Nantista, Christopher; Osborne, John; Palmer, Mark; Paterson, James McEwan; Peterson, Thomas; Phinney, Nan; Pierini, Paolo; Ross, Marc; Rubin, David; Seryi, Andrei; Sheppard, John; Solyak, Nikolay; Stapnes, Steinar; Tauchi, Toshiaki; Toge, Nobu; Walker, Nicholas; Yamamoto, Akira; Yokoya, Kaoru

    2013-01-01

    The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to incr...

  11. Summary of IAEA technical committee meeting on impurity control

    International Nuclear Information System (INIS)

    Itoh, Kimitaka.

    1989-03-01

    Presentations given in the IAEA technical committee meeting on impurity control (held in JAERI from 13 to 15 February, 1989) are summarized, putting the emphasis on the physics modelling of the plasma related to the impurity production and confinement. (author)

  12. Proceedings of the ninth annual DOE low-level waste management forum: executive summary, technical and special session summaries, attendees

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    This first volume of proceedings contains summaries of each of six technical sessions as well as three special sessions held during the conference. The six technical sessions were: Disposal technology and facility development (15 papers); Institutional and regulatory issues (10); Performance assessment (14); Waste characterization and verification (7); Site closure and stabilization (6); and Waste treatment (8). The three special sessions were: 1) Review of criteria for guidance on alternative disposal technology; 2) Hazardous waste regulatory update; and 3) Challenges to meeting the 1993 deadline. All papers have been indexed for inclusion on the Energy Data Base

  13. 2011 Residential Energy Efficiency Technical Update Meeting Summary Report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2011-11-01

    This report provides an overview of the U.S. Department of Energy Building America program's Summer 2011 Residential Energy Efficiency Technical Update Meeting. This meeting was held on August 9-11, 2011, in Denver, Colorado, and brought together more than 290 professionals representing organizations with a vested interest in energy efficiency improvements in residential buildings.

  14. F/H effluent treatment facility. Technical data summary

    International Nuclear Information System (INIS)

    Ryan, J.P.; Stimson, R.E.

    1984-12-01

    This document provides the technical basis for the design of the facility. Some of the sections are described with options to permit simplification of the process, depending on the effluent quality criteria that the facility will have to meet. Each part of the F/HETF process is reviewed with respect to decontamination and concentration efficiency, operability, additional waste generation, energy efficiency, and compatability with the rest of the process

  15. Organic Contamination Baseline Study: In NASA JSC Astromaterials Curation Laboratories. Summary Report

    Science.gov (United States)

    Calaway, Michael J.

    2013-01-01

    In preparation for OSIRIS-REx and other future sample return missions concerned with analyzing organics, we conducted an Organic Contamination Baseline Study for JSC Curation Labsoratories in FY12. For FY12 testing, organic baseline study focused only on molecular organic contamination in JSC curation gloveboxes: presumably future collections (i.e. Lunar, Mars, asteroid missions) would use isolation containment systems over only cleanrooms for primary sample storage. This decision was made due to limit historical data on curation gloveboxes, limited IR&D funds and Genesis routinely monitors organics in their ISO class 4 cleanrooms.

  16. Critical evaluation of the nonradiological environmental technical specifications. Program description, summary, and recommendations. Vol. 1

    International Nuclear Information System (INIS)

    Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.; Witten, A.J.

    1976-01-01

    A comprehensive study of the data collected as part of the environmental Technical Specifications program for eight nuclear power plants was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory commission. This report includes a summary of the screening phase in which the adequacy of the hydrothermal and ecological monitoring data for each plant were evaluated, and the summary and recommendations resulting from a detailed examination of the three nuclear power plants selected in the initial screening

  17. Baseline tests for arc melter vitrification of INEL buried wastes. Volume 1: Facility description and summary data report

    International Nuclear Information System (INIS)

    Oden, L.L.; O'Connor, W.K.; Turner, P.C.; Soelberg, N.R.; Anderson, G.L.

    1993-01-01

    This report presents field results and raw data from the Buried Waste Integrated Demonstration (BWID) Arc Melter Vitrification Project Phase 1 baseline test series conducted by the Idaho National Engineering Laboratory (INEL) in cooperation with the U.S. Bureau of Mines (USBM). The baseline test series was conducted using the electric arc melter facility at the USBM Albany Research Center in Albany, Oregon. Five different surrogate waste feed mixtures were tested that simulated thermally-oxidized, buried, TRU-contaminated, mixed wastes and soils present at the INEL. The USBM Arc Furnace Integrated Waste Processing Test Facility includes a continuous feed system, the arc melting furnace, an offgas control system, and utilities. The melter is a sealed, 3-phase alternating current (ac) furnace approximately 2 m high and 1.3 m wide. The furnace has a capacity of 1 metric ton of steel and can process as much as 1,500 lb/h of soil-type waste materials. The surrogate feed materials included five mixtures designed to simulate incinerated TRU-contaminated buried waste materials mixed with INEL soil. Process samples, melter system operations data and offgas composition data were obtained during the baseline tests to evaluate the melter performance and meet test objectives. Samples and data gathered during this program included (a) automatically and manually logged melter systems operations data, (b) process samples of slag, metal and fume solids, and (c) offgas composition, temperature, velocity, flowrate, moisture content, particulate loading and metals content. This report consists of 2 volumes: Volume I summarizes the baseline test operations. It includes an executive summary, system and facility description, review of the surrogate waste mixtures, and a description of the baseline test activities, measurements, and sample collection. Volume II contains the raw test data and sample analyses from samples collected during the baseline tests

  18. International Code Centres Network. Summary Report of the Technical Meeting

    International Nuclear Information System (INIS)

    Chung, H-K.

    2011-01-01

    Fifteen international experts on computational aspects of atomic, molecular and particle surface interaction data for fusion energy research participated in the 2nd technical meeting of the International Code Centres Network. Participants reported their research on data production and computational capabilities at their institutions. Experts in the field of plasma modeling of magnetic fusion research joined this meeting to present the data needs and bring the perspective of data users. The interaction and discussion among data producers and data users in this two-day meeting led to an agreement that the scope and function of Code Centres Network should be reformulated to serve the needs of fusion community in more effective way. (author)

  19. Summary report on [IAEA] technical meeting of the International Network of Nuclear Reaction Data Centres

    International Nuclear Information System (INIS)

    Dunaeva, S.; Otsuka, N.; Schwerer, O.

    2009-08-01

    An IAEA Technical Meeting of the International Network of Nuclear Reaction Data Centres was held at the IAEA Headquarters in Vienna from 25 to 26 May 2009. The meeting was attended by 23 participants from 13 cooperating data centres. A summary of the meeting is given in this report, along with the conclusions, actions, and status report of the participating data centres. (author)

  20. NEXT-100 Technical Design Report (TDR). Executive summary

    International Nuclear Information System (INIS)

    Álvarez, V; Cárcel, S; Cervera, A; Díaz, J; Ferrario, P; Borges, F I G M; Conde, C A N; Dias, T H V T; Fernandes, L M P; Carmona, J M; Castel, J; Cebrián, S; Dafni, T; Catalá, J M; Esteve, R; Chan, D; Egorov, M; Evtoukhovitch, P; Ferreira, A L; Ferrer-Ribas, E

    2012-01-01

    In this Technical Design Report (TDR) we describe the NEXT-100 detector that will search for neutrinoless double beta decay (ββ0ν) in 136 XE at the Laboratorio Subterráneo de Canfranc (LSC), in Spain. The document formalizes the design presented in our Conceptual Design Report (CDR): an electroluminescence time projection chamber, with separate readout planes for calorimetry and tracking, located, respectively, behind cathode and anode. The detector is designed to hold a maximum of about 150 kg of xenon at 15 bar, or 100 kg at 10 bar. This option builds in the capability to increase the total isotope mass by 50% while keeping the operating pressure at a manageable level. The readout plane performing the energy measurement is composed of Hamamatsu R11410-10 photomultipliers, specially designed for operation in low-background, xenon-based detectors. Each individual PMT will be isolated from the gas by an individual, pressure resistant enclosure and will be coupled to the sensitive volume through a sapphire window. The tracking plane consists in an array of Hamamatsu S10362-11-050P MPPCs used as tracking pixels. They will be arranged in square boards holding 64 sensors (8 × 8) with a 1-cm pitch. The inner walls of the TPC, the sapphire windows and the boards holding the MPPCs will be coated with tetraphenyl butadiene (TPB), a wavelength shifter, to improve the light collection.

  1. NEXT-100 Technical Design Report (TDR). Executive summary

    Science.gov (United States)

    Álvarez, V.; Borges, F. I. G. M.; Cárcel, S.; Carmona, J. M.; Castel, J.; Catalá, J. M.; Cebrián, S.; Cervera, A.; Chan, D.; Conde, C. A. N.; Dafni, T.; Dias, T. H. V. T.; Díaz, J.; Egorov, M.; Esteve, R.; Evtoukhovitch, P.; Fernandes, L. M. P.; Ferrario, P.; Ferreira, A. L.; Ferrer-Ribas, E.; Freitas, E. D. C.; Gehman, V. M.; Gil, A.; Giomataris, I.; Goldschmidt, A.; Gómez, H.; Gómez-Cadenas, J. J.; González, K.; González-Díaz, D.; Gutiérrez, R. M.; Hauptman, J.; Hernando Morata, J. A.; Herrera, D. C.; Herrero, V.; Iguaz, F. J.; Irastorza, I. G.; Kalinnikov, V.; Kiang, D.; Labarga, L.; Liubarsky, I.; Lopes, J. A. M.; Lorca, D.; Losada, M.; Luzón, G.; Marí, A.; Martín-Albo, J.; Martínez, A.; Miller, T.; Moiseenko, A.; Monrabal, F.; Monteiro, C. M. B.; Monzó, J. M.; Mora, F. J.; Moutinho, L. M.; Muñoz Vidal, J.; Natal da Luz, H.; Navarro, G.; Nebot, M.; Nygren, D.; Oliveira, C. A. B.; Palma, R.; Pérez, J.; Pérez Aparicio, J. L.; Renner, J.; Ripoll, L.; Rodríguez, A.; Rodríguez, J.; Santos, F. P.; dos Santos, J. M. F.; Segui, L.; Serra, L.; Shuman, D.; Sofka, C.; Sorel, M.; Toledo, J. F.; Tomás, A.; Torrent, J.; Tsamalaidze, Z.; Vázquez, D.; Velicheva, E.; Veloso, J. F. C. A.; Villar, J. A.; Webb, R. C.; Weber, T.; White, J.; Yahlali, N.

    2012-06-01

    In this Technical Design Report (TDR) we describe the NEXT-100 detector that will search for neutrinoless double beta decay (ββ0ν) in 136XE at the Laboratorio Subterráneo de Canfranc (LSC), in Spain. The document formalizes the design presented in our Conceptual Design Report (CDR): an electroluminescence time projection chamber, with separate readout planes for calorimetry and tracking, located, respectively, behind cathode and anode. The detector is designed to hold a maximum of about 150 kg of xenon at 15 bar, or 100 kg at 10 bar. This option builds in the capability to increase the total isotope mass by 50% while keeping the operating pressure at a manageable level. The readout plane performing the energy measurement is composed of Hamamatsu R11410-10 photomultipliers, specially designed for operation in low-background, xenon-based detectors. Each individual PMT will be isolated from the gas by an individual, pressure resistant enclosure and will be coupled to the sensitive volume through a sapphire window. The tracking plane consists in an array of Hamamatsu S10362-11-050P MPPCs used as tracking pixels. They will be arranged in square boards holding 64 sensors (8 × 8) with a 1-cm pitch. The inner walls of the TPC, the sapphire windows and the boards holding the MPPCs will be coated with tetraphenyl butadiene (TPB), a wavelength shifter, to improve the light collection.

  2. IAEA technical meeting on 'Technical aspects of atomic and molecular data processing and exchange'. Summary report

    International Nuclear Information System (INIS)

    Humbert, Denis

    2004-03-01

    The proceedings of the IAEA Advisory Group Meeting on 'Technical Aspects of Atomic and Molecular Data Processing and Exchange' (17th Meeting of A+M Data Centres and ALADDIN Network), held on 6-7 October, 2003 in Vienna, Austria are briefly described. The meeting conclusions and recommendations on the priorities in A+M data compilation and evaluation, and on the technical aspects of data processing, exchange, and distribution are also presented. (author)

  3. Estimating the Cold War mortgage: The 1995 Baseline Environmental Management report. Executive summary, March 1995

    International Nuclear Information System (INIS)

    1995-01-01

    This is the first annual report on the activities and potential costs required to address the waste, contamination, and surplus nuclear facilities that are the responsibility of DOE's Environmental Management program. Of the Base Case life-cycle cost estimate of $230 billion from 1995 to 2070, 49% is waste management, 28% environmental restoration, 10% nuclear material and facility stabilization, 5% technology development, and 8% other. The top 5 sites account for 70% of the costs: Hanford 21%, Savannah River Site 21%, Rocky Flats 10%, Oak Ridge 10%, and Idaho Laboratory 8%. Assumptions include significant productivity increases, meeting current compliance requirements, and use of existing technologies. Excluded were: cleanup where no feasible cleanup technology exists (eg, nuclear explosion sites and most contaminated groundwater), cleanup of currently active facilities, naval nuclear propulsion facilities (handled by US Navy), and first 5 years of program ($23 billion). Of the alternative cases evaluated, land use has the biggest potential cost impact. Total projected environmental costs are comparable to total U.S. nuclear weapons production costs. The makeup of Volumes I and II (the latter being site summaries) are outlined briefly

  4. Technical Working Group on Career and Technical Education Meeting. Meeting Summary (Washington, DC, September 22, 2017)

    Science.gov (United States)

    Ahn, Judie

    2017-01-01

    On September 22, 2017, the National Center for Special Education Research (NCSER) and the National Center for Education Research (NCER) at the Institute of Education Sciences (IES) convened a group of experts in policy, practice, and research related to Career and Technical Education (CTE). The goal of the meeting was to seek input from…

  5. CALS Baseline Architecture Analysis of Weapons System. Technical Information: Army, Draft. Volume 8

    Science.gov (United States)

    1989-09-01

    This effort was performed to provide a common framework for analysis and planning of CALS initiatives across the military services, leading eventually to the development of a common DoD-wide architecture for CALS. This study addresses Army technical ...

  6. Yucca Mountain Project: A summary of technical support activities, January 1987--June 1988

    International Nuclear Information System (INIS)

    1989-05-01

    This report is a summary of the technical support activities of Mifflin ampersand Associates, Inc., during the 18-month period beginning 01 January 1987 and ending on 30 June 1988. It covers the following topics: Vadose zone drilling site selection, permits and quality assurance (QA) procedures; climate change; geochemistry, mineralogy; disturbed zone; hydrogeology; and review of technical documents. The report is organized by generally discussing each topic from the following perspectives: issue(s), objective(s) of activity, finding(s), interpretation of finding(s), additional work needed, recommended program, and existing program

  7. Summary of the technical guidelines used in the project: The economics of greenhouse gas limitations

    International Nuclear Information System (INIS)

    Halsnaes, Kirsten

    1998-01-01

    This document is a summary version of the technical guidelines for climate change mitigation assessment developed as a part of the Global Environment Facility (GEF) project The Economics of Greenhouse Gas Limitations; Technical guidelines (UNEP 1998). The objectives of this project have been to support the development of a methodology, an implementing framework and a reporting system which countries can use in the construction of national climate change policies and in meeting their future reporting obligations under the FCCC. The methodological framework developed in the guidelines covers key economic concepts, scenario building, modelling tools and common assumptions. It was used by several country studies included in the project. (au)

  8. Technical Summary

    NARCIS (Netherlands)

    Arvizu, D.; Faaij, A.P.C.

    2011-01-01

    All societies requir e energy services to meet basic human needs (e.g., lighting, cooking, space comfort, mobility, communication) and to serve productive processes. For development to be sustainable, delivery of energy services needs to be secure and have low environmental impacts. Sustainable

  9. Summary Report of the Technical Meeting on International Network of Nuclear Reaction Data Centres

    International Nuclear Information System (INIS)

    Otsuka, Naohiko

    2012-06-01

    This report summarizes the IAEA Technical Meeting on the International Network of Nuclear Reaction Data Centres, held at the OECD Nuclear Energy Agency (NEA) in Issy-les-Moulineaux, France from 16 to 19 April 2012. The meeting was attended by twenty-three participants representing thirteen cooperative centres from eight Member States and two International Organisations. A summary of the meeting is given in this report along with the conclusions and actions. (author)

  10. KBS Annual Report 1982. Summaries of technical reports issued during 1982

    International Nuclear Information System (INIS)

    1983-07-01

    The purpose of the KBS Annual Report is to inform interested organizations and individuals of the research and development work perfomed by the division KBS within the Swedish Nuclear Fuel Supply Co. (SKBF) on the handling, treatment and final storage of nuclear wastes in Sweden. In the Annual Report for 1982 the summaries of 27 technical reports and other publications issued during the year are listed. (K.A.E.)

  11. Summary Report on IAEA Technical Meeting on the International Network of Nuclear Reaction Data Centres

    International Nuclear Information System (INIS)

    Otsuka, Naohiko

    2011-07-01

    This report summarizes the IAEA Technical Meeting of the International Network of Nuclear Reaction Data Centres, held at the IAEA Headquarters in Vienna, Austria from 23 - 24 May 2011. The meeting was attended by 25 participants from 13 cooperating data centres of nine Member States and two International Organizations. The report contains a summary of the meeting, the conclusions and actions, the lists of working papers and presentations presented at the meeting. (author)

  12. Summary Report of the Technical Meeting on International Network of Nuclear Reaction Data Centres

    International Nuclear Information System (INIS)

    Otsuka, Naohiko

    2013-07-01

    This report summarizes the IAEA Technical Meeting on the International Network of Nuclear Reaction Data Centres, held at the IAEA Headquarters in Vienna, Austria from 23 to 25 April 2013. The meeting was attended by 24 participants representing 13 cooperative centres from 8 Member States and 2 International Organisations. A summary of the meeting is given in this report along with the conclusions and actions. (author)

  13. Technology status in support of refined technical baseline for the Spent Nuclear Fuel project. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Puigh, R.J.; Toffer, H.; Heard, F.J.; Irvin, J.J.; Cooper, T.D.

    1995-10-20

    The Spent Nuclear Fuel Project (SNFP) has undertaken technology acquisition activities focused on supporting the technical basis for the removal of the N Reactor fuel from the K Basins to an interim storage facility. The purpose of these technology acquisition activities has been to identify technology issues impacting design or safety approval, to establish the strategy for obtaining the necessary information through either existing project activities, or the assignment of new work. A set of specific path options has been identified for each major action proposed for placing the N Reactor fuel into a ``stabilized`` form for interim storage as part of this refined technical basis. This report summarizes the status of technology information acquisition as it relates to key decisions impacting the selection of specific path options. The following specific categories were chosen to characterize and partition the technology information status: hydride issues and ignition, corrosion, hydrogen generation, drying and conditioning, thermal performance, criticality and materials accountability, canister/fuel particulate behavior, and MCO integrity. This report represents a preliminary assessment of the technology information supporting the SNFP. As our understanding of the N Reactor fuel performance develops the technology information supporting the SNFP will be updated and documented in later revisions to this report. Revision 1 represents the incorporation of peer review comments into the original document. The substantive evolution in our understanding of the technical status for the SNFP (except section 3) since July 1995 have not been incorporated into this revision.

  14. Technology status in support of refined technical baseline for the Spent Nuclear Fuel project. Revision 1

    International Nuclear Information System (INIS)

    Puigh, R.J.; Toffer, H.; Heard, F.J.; Irvin, J.J.; Cooper, T.D.

    1995-01-01

    The Spent Nuclear Fuel Project (SNFP) has undertaken technology acquisition activities focused on supporting the technical basis for the removal of the N Reactor fuel from the K Basins to an interim storage facility. The purpose of these technology acquisition activities has been to identify technology issues impacting design or safety approval, to establish the strategy for obtaining the necessary information through either existing project activities, or the assignment of new work. A set of specific path options has been identified for each major action proposed for placing the N Reactor fuel into a ''stabilized'' form for interim storage as part of this refined technical basis. This report summarizes the status of technology information acquisition as it relates to key decisions impacting the selection of specific path options. The following specific categories were chosen to characterize and partition the technology information status: hydride issues and ignition, corrosion, hydrogen generation, drying and conditioning, thermal performance, criticality and materials accountability, canister/fuel particulate behavior, and MCO integrity. This report represents a preliminary assessment of the technology information supporting the SNFP. As our understanding of the N Reactor fuel performance develops the technology information supporting the SNFP will be updated and documented in later revisions to this report. Revision 1 represents the incorporation of peer review comments into the original document. The substantive evolution in our understanding of the technical status for the SNFP (except section 3) since July 1995 have not been incorporated into this revision

  15. Technical summary of geological, hydrological, and engineering studies at the Slick Rock Uranium Mill Tailings sites, Slick Rock, Colorado

    International Nuclear Information System (INIS)

    1990-12-01

    The purpose of this document is to provide the Colorado Department of Health (CDH) with a summary of the technical aspects of the proposed remedial action for the Slick Rock tailings near Slick Rock, Colorado. The technical issues summarized in this document are the geology and groundwater at the Burro Canyon disposal site and preliminary engineering considerations for the disposal cell

  16. The Agency's technical co-operation programme with Thailand 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Thailand carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  17. The Agency's technical co-operation programme with Sri Lanka 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Sri Lanka carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  18. Summary Report of the Technical Meeting on International Network of Nuclear Reaction Data Centres

    International Nuclear Information System (INIS)

    Otuka, Naohiko; Herman, Michal

    2016-07-01

    This report summarizes the IAEA Technical Meeting on the International Network of Nuclear Reaction Data Centres held at the China Hall of Science and Technology in Beijing, China from 7 to 10 June 2016. The meeting was attended by 23 participants representing 13 cooperative Centres from 8 Member States (China, Hungary, India, Japan, Korea, Russia, Ukraine and USA) and 2 International Organisations (NEA, IAEA) as well as two participants from Kazakhstan. A summary of the meeting is given in this report along with the conclusions and actions. (author)

  19. The Agency's technical co-operation programme with Bolivia 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Bolivia carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  20. The Agency's technical co-operation programme with Panama 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Panama carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  1. The Agency's technical co-operation programme with Bangladesh 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Bangladesh carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  2. The Agency's technical co-operation programme with Panama 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in Panama carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  3. The Agency's technical co-operation programme with Guatemala 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in Guatemala carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  4. The Agency's technical co-operation programme with Iceland 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Iceland carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  5. The Agency's technical co-operation programme with Bangladesh 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Bangladesh carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  6. The Agency's technical co-operation programme with Cyprus 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Cyprus carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  7. The Agency's technical co-operation programme with Albania 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Albania carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  8. The Agency's technical co-operation programme with Indonesia 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Indonesia carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  9. The Agency's technical co-operation programme with Poland 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Poland carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  10. The Agency's technical co-operation programme with Romania 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Romania carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  11. The Agency's technical co-operation programme with Viet Nam 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Viet Nam carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  12. The Agency's technical co-operation programme with the Philippines 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in Philippines carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  13. The Agency's technical co-operation programme with The Philippines 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in The Philippines carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  14. The Agency's technical co-operation programme with Greece 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Greece carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  15. The Agency's technical co-operation programme with Dominican Republic 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Dominican Republic carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  16. The Agency's technical co-operation programme with Nicaragua 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Nicaragua carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  17. The Agency's technical co-operation programme with Afghanistan 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Afghanistan carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  18. The Agency's technical co-operation programme with Jamaica 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Jamaica carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  19. The Agency's technical co-operation programme with Ecuador 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Ecuador carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  20. The Agency's technical co-operation programme with El Salvador 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in El Salvador carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  1. The Agency's technical co-operation programme with Nigeria 1986-1996 country programme summaries

    International Nuclear Information System (INIS)

    1996-01-01

    This report contains a review of the Agency's technical co-operation activities in Nigeria carried out during 1986-1996. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  2. The Agency's technical co-operation programme with Bolivia 1986-1996 country programme summaries

    International Nuclear Information System (INIS)

    1996-01-01

    This report contains a review of the Agency's technical co-operation activities in Bolivia carried out during 1986-1996. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  3. The Agency's technical co-operation programme with Colombia 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Colombia carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  4. The Agency's technical co-operation programme with Portugal 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Portugal carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  5. The Agency's technical co-operation programme with Pakistan 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in Pakistan carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  6. Summary of Tiger Team Assessment and Technical Safety Appraisal recurring concerns in the Maintenance Area

    International Nuclear Information System (INIS)

    1993-01-01

    Tiger Team Assessments and Technical Safety Appraisals (TSA) were reviewed and evaluated for concerns in the Maintenance Area (MA). Two hundred and thirty one (231) maintenance concerns were identified by the Tiger Team Assessments and TSA reports. These recurring concerns appear below. A summary of the Noteworthy Practices that were identified and a compilation of the maintenance concerns for each performance objective that were not considered as recurring are also included. Where the Tiger Team Assessment and TSA identified the operating contractor or facility by name, the concern has been modified to remove the name while retaining the intent of the comment

  7. The Agency's technical co-operation programme with Myanmar 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in Myanmar carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  8. The Agency's technical co-operation programme with Malaysia 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Malaysia carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  9. The Agency's technical co-operation programme with Jordan 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Jordan carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  10. The Agency's technical co-operation programme with Mongolia 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in Mongolia carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  11. The Agency's technical co-operation programme with Egypt 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in Egypt carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  12. The Agency's technical co-operation programme with Paraguay 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Paraguay carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  13. The Agency's technical co-operation programme with Mexico 1986-1996 country programme summaries

    International Nuclear Information System (INIS)

    1996-01-01

    This report contains a review of the Agency's technical co-operation activities in Mexico carried out during 1986-1996. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  14. The Agency's technical co-operation programme with Paraguay 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Paraguay carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  15. The Agency's technical co-operation programme with Hungary 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Hungary carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  16. SCFA lead lab technical assistance at Lawrence Berkeley National Laboratory: Baseline review of three groundwater plumes

    Energy Technology Data Exchange (ETDEWEB)

    Hazen, Terry; et al.

    2002-09-26

    During the closeout session, members of the technical assistance team conveyed to the site how impressed they were at the thoroughness of the site's investigation and attempts at remediation. Team members were uniformly pleased at the skilled detection work to identify sources, make quick remediation decisions, and change course when a strategy did not work well. The technical assistance team also noted that, to their knowledge, this is the only DOE site at which a world-class scientist has had primary responsibility for the environmental restoration activities. This has undoubtedly contributed to the successes observed and DOE should take careful note. The following overall recommendations were agreed upon: (1) The site has done a phenomenal job of characterization and identifying and removing source terms. (2) Technologies selected to date are appropriate and high impact, e.g. collection trenches are an effective remedial strategy for this complicated geology. The site should continue using technology that is adapted to the site's unique geology, such as the collection trenches. (3) The site should develop a better way to determine the basis of cleanup for all sites. (4) The sentinel well system should be evaluated and modified, if needed, to assure that the sentinel wells provide coverage to the current site boundary. Potential modifications could include installation, abandonment or relocation of wells based on the large amount of data collected since the original sentinel well system was designed. (5) Modeling to assist in remedial design and communication should continue. (6) The site should develop a plan to ensure institutional memory. (7) The most likely possibility for improving closure to 2006 is by removing the residual source of the Old Town plume and establishing the efficacy of remediation for the 51/64 plume.

  17. The Agency's Technical Co-operation programme with Kenya, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With almost $3.9 million of Agency support received, Kenya ranks 39th among all recipients of technical assistance during the period 1958-1991. Almost half of the assistance during the past ten years has been provided in the form of the equipment (44%), followed by training (33%) and expert services (23%). Two-thirds of the funds available were provided by the Technical Assistance and Co-operation Fund (66%), while extra-budgetary contributions accounted for 18%, in-kind contributions for 14%, and UNDP for 2% of the resources. With regard to project disbursements during the past ten years, by sector, the four major areas have been general atomic energy development (30%), agriculture (22%), nuclear medicine and nuclear safety (13% each)

  18. The Agency's Technical Co-operation programme with Niger, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With some $1.5 million of Agency support received, Niger ranks 65th among all recipients of technical assistance in the period 1958 through 1991. About two-thirds of the assistance received during the past ten years has been provided in the form of equipment (62%), complemented by expert services (26%) and training (12%). Almost the entire resources utilized were provided by the Technical Assistance and Co-operation Fund (96%), with only a small share made available through assistance in kind (4%). With regard to project disbursements by sector, the four major areas have been agriculture (34%), general atomic energy development (31%), hydrology (18%) and nuclear safety (12%)

  19. The Agency's Technical Co-operation programme with Sierra Leone, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $1.1 million of Agency support received, Sierra Leone ranks 70th among all recipients of technical assistance in the period 1958 through 1991. Almost equal shares of the assistance during the past ten years have been provided in the form of equipment (40%) and expert services (37%), while the share of the training component was 23%. The best part of the resources was provided by the Technical Assistance and Co-operation Fund (96%), the remaining 4% was made available through assistance in kind. During the past ten years, project activities - and disbursements - have concentrated exclusively on three major areas: nuclear medicine (52%), general atomic energy development (25%) and agriculture (23%)

  20. The Agency's Technical Co-operation programme with Cameroon, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With $1.3 million of Agency support received, Cameroon ranks 68th among all recipients of technical assistance in the period 1958 through 1991. More than half of the assistance received during the past ten years has been provided in the form of equipment (61%), followed by expert services (24%) and training (15%). The best part of the resources were provided by the Technical Assistance and Co-operation Fund (90%); the remaining ten per cent were made available through extrabudgetary contributions (8%) and assistance in kind (2%). With regard to project disbursements by sector, the four major areas have been nuclear physics and chemistry (38%), agriculture (23%), nuclear medicine (14%) and hydrology (13%)

  1. The Agency's Technical Co-operation programme with Mali, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $2.7 million of Agency support received, Mali ranks 51st among all recipients of technical assistance in the period 1958 through 1991. More than half of the assistance during the past ten years has been provided in the form of equipment (58%), followed by expert services (27%) and training (15%). With a share of 93%, the Technical Assistance and Co-operation Fund has provided the best part of the resources, while only very small shares were made available through extrabudgetary contributions and assistance in kind (5% and 2%, respectively). With regard to project disbursements during the past ten years, by sector, the four major areas have been hydrology (31%), nuclear medicine (24%), agriculture (21%) and nuclear raw materials (16%)

  2. The Agency's Technical Co-operation programme with Costa Rica, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $2.8 million of Agency support received, Costa Rica ranks 49th among all recipients of technical assistance in the period 1958-1991. Over half of the assistance during the past ten years has been provided in the form of equipment (52%), followed by expert services (37%) and training (11%). Sixty-two per cent of the resources were made available through the Technical Assistance and Co-operation Fund, while 37% of the resources were provided by UNDP. The rest was made available through extrabudgetary contributions (5%) and through in-kind assistance (1%). With regard to project disbursement by sector, the largest areas have been nuclear raw materials (36%), nuclear physics and chemistry (24%) and agriculture (20%). Smaller shares have gone to hydrology (11%) and nuclear medicine (8%)

  3. The Agency's Technical Co-operation programme with Zambia, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With $5.5 million of Agency support received, Zambia ranks 33rd among all recipients of technical assistance in the period 1958 through 1991. More than half of the assistance during the past ten years has been provided in the form of equipment (61%), followed by expert services (25%) and training (14%). Almost all of the resources made available came from the Technical Assistance and Co-operation Fund (93%), with only very small shares provided through extrabudgetary contributions (4%) and assistance in kind (3%). With regard to project disbursements during the past ten years, by sector, the largest areas have been agriculture (33%) and general atomic energy development (23%), followed by industry and hydrology (19%), nuclear raw materials (13%) and nuclear safety (6%)

  4. The Agency's Technical Co-operation programme with Algeria, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With $3.6 million of Agency support received, Algeria ranks 41st among all recipients of technical assistance in the period 1958-1991. Seventy per cent of the assistance received during the past ten years has been in the form of equipment, followed by expert services (17%) and training (13%). Almost all of the resources were provided by the Technical Assistance and Co-operation Fund (97%), the remaining 3% were made available through assistance in kind. With regard to project disbursement by sector, the three major areas have been nuclear physics and chemistry (28%), agriculture (27%) and nuclear medicine (20%)

  5. The Agency's Technical Co-operation programme with Ethiopia, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With some $2.5 million of Agency support received, Ethiopia ranks 54th among all recipients of technical assistance in the period 1958 through 1991. More than half of the assistance received during the past ten years has been provided in the form of equipment (55%), complemented by expert services (16%) and training (29%). The best part of the resources was provided by the Technical Assistance and Co-operation Fund (88%), the remainder was made available through assistance in kind (6%), UNDP and extrabudgetary contributions (3% each). During the past ten years, project disbursements went to four major areas: agriculture (45%), nuclear medicine (35%), nuclear safety (14%) and nuclear engineering and technology (6%)

  6. The Agency's Technical Co-operation programme with Guatemala, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $3 million of Agency support received, Guatemala ranks 46th among all recipients of technical assistance in the period 1958 - 1991. Almost three quarters of the assistance during the past ten years has been provided in the form of equipment (72%), followed by training (15%) and expert services (13%). Seventy-eight per cent of the resources were provided by the Technical Assistance and Co-operation Fund, the rest was made available through extrabudgetary contributions (21%) and assistance in kind (1%). With regard to project disbursement by sector, the largest areas have been nuclear physics and chemistry (37%), agriculture (28%), nuclear medicine (16%) and hydrology (8%). The remaining 11% were shared by general atomic energy development, nuclear raw materials, nuclear engineering and technology, and nuclear safety

  7. The Agency's Technical Co-operation programme with Mexico, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With almost $7.7 million of Agency support received, Mexico ranks 21st among all recipients of technical assistance during the period 1958 through 1991. The largest share of the assistance received during the past ten years has been in the form of expert services (36%), followed by equipment and training (27% each) and sub-contracts (10%). Almost two-thirds of the funds available were provided by the Technical Assistance and Co-operation Fund (65%), the rest was made available through extrabudgetary contributions (21%) and assistance in kind (14%). With regard to project disbursements during the past ten years, by sector the five major areas have been nuclear safety (34%), nuclear engineering and technology (27%), agriculture (17%), nuclear physics and chemistry (9%), and nuclear techniques in industry and hydrology (9%)

  8. The Agency's Technical Co-operation programme with Uganda, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With $1.6 million of Agency support received, Uganda ranks 61st among all recipients of technical assistance in the period 1958 through 1991. Almost half of the assistance received during the past ten years has been provided in the form of equipment (47%), complemented by a strong training component (37%), while expert services have received only a relatively small share (16%). Ninety-eight per cent of the resources were provided by the Technical Assistance and Co-operation Fund, the remaining two per cent were made available through assistance in kind. During the past ten years, project activities - and disbursements - have concentrated exclusively on three major areas: agriculture (64%), nuclear medicine (24%) and nuclear safety (12%)

  9. The Agency's Technical Co-operation programme with Uruguay, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $4.2 million of Agency support received, Uruguay ranks 37th among all recipients of technical assistance in the period 1958 - 1991. More than half of the assistance during the past ten years has been provided in the form of equipment (67%), followed by expert services (19%) and training (14%). Seventy-three per cent of the resources were provided through the Technical Assistance and Co-operation Fund, while 24% were made available through extrabudgetary contributions. The remaining 3% were provided through assistance in kind, with only an insignificant contribution by UNDP. With regard to project disbursement by sector, the largest areas have been nuclear medicine (35%), agriculture (23%), general atomic energy development (17%), followed by nuclear physics and chemistry (11%) and industry and hydrology (7%)

  10. The Agency's Technical Co-operation programme with Zaire, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With $3.9 million of Agency support received, Zaire ranks 38th among all recipients of technical assistance in the period 1958 through 1991. More than half of the assistance during the past ten years has been provided in the form of equipment (60%), followed by training (24%) and expert services (16%). With a share of 76%, the Technical Assistance and Co-operation Fund has provided more than three quarters of the total resources available, while only small shares were made available through UNDP (11%), extrabudgetary contributions (4%) and assistance in kind (9%). With regard to project disbursements during the past ten years, by sector, the largest area has been general atomic energy development (26%), followed by agriculture (18%), nuclear safety (18%), nuclear techniques in industry and hydrology (13%), and nuclear physics and chemistry (11%)

  11. The Agency's Technical Co-operation programme with Nigeria, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $9.3 million of Agency support received, Nigeria ranks 14th among all recipients of technical assistance in the period 1958 through 1991. During the past ten years, 44% of this assistance has been provided in the form of equipment, followed by training (27%), expert services (26%) and sub-contracts (3%). With 45% and 44%, respectively, the Technical Assistance and Co-operation Fund and extrabudgetary contributions hold almost equal shares in the total resources made available, while in-kind assistance accounts for 9% and UNDP for 2% of the resources. With regard to project disbursement during the past ten years, by sector, by far the largest area has been agriculture (70%), with significantly smaller shares going to nuclear physics and chemistry (11%), nuclear medicine (8%) and nuclear safety (7%)

  12. The Agency's Technical Co-operation programme with Senegal, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With $2.2 million of Agency support received, Senegal ranks 56th among all recipients of technical assistance in the period 1958 - 1991. More than one-third of the assistance during the past ten years has been provided in the form of equipment (67%), followed by expert services (21%) and training (12%). Eighty per cent of the resources were provided by the Technical Assistance and Co-operation Fund, while 16% were made available by UNDP and about 2% each through extrabudgetary contributions and assistance in kind. With regard to project disbursement by sector, by far the largest area has been agriculture (43%). Smaller shares have gone to general atomic energy development (15%), nuclear physics and chemistry (13%), nuclear medicine and hydrology (11% each), and nuclear safety (7%)

  13. Revision of the European Ecolabel Criteria for Personal, Notebook and Tablet Computers TECHNICAL REPORT Summary of the final criteria proposals

    OpenAIRE

    DODD NICHOLAS; VIDAL ABARCA GARRIDO CANDELA; WOLF Oliver; GRAULICH Kathrin; BUNKE Dirk; GROSS Rita; LIU Ran; MANHART Andreas; PRAKASH Siddharth

    2015-01-01

    This technical report provide the background information for the revision of the EU Ecolabel criteria for Personal and Notebook Computers. The study has been carried out by the Joint Research Centre with technical support from the Oeko-Institut. The work has been developed for the European Commission's Directorate General for the Environment. The main purpose of this report is to provide a summary of the technical background and rationale for each criterion proposal. This document is compl...

  14. Weeks Island brine diffuser site study: baseline conditions and environmental assessment technical report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-12-12

    This technical report presents the results of a study conducted at two alternative brine diffuser sites (A and B) proposed for the Weeks Island salt dome, together with an analysis of the potential physical, chemical, and biological effects of brine disposal for this area of the Gulf of Mexico. Brine would result from either the leaching of salt domes to form or enlarge oil storage caverns, or the subsequent use of these caverns for crude oil storage in the Strategic Petroleum Reserve (SPR) program. Brine leached from the Weeks Island salt dome would be transported through a pipeline which would extend from the salt dome either 27 nautical miles (32 statute miles) for Site A, or 41 nautical miles (47 statute miles) for Site B, into Gulf waters. The brine would be discharged at these sites through an offshore diffuser at a sustained peak rate of 39 ft/sup 3//sec. The disposal of large quantities of brine in the Gulf could have a significant impact on the biology and water quality of the area. Physical and chemical measurements of the marine environment at Sites A and B were taken between September 1977 and July 1978 to correlate the existing environmental conditions with the estimated physical extent of tthe brine discharge as predicted by the MIT model (US Dept. of Commerce, 1977a). Measurements of wind, tide, waves, currents, and stratification (water column structure) were also obtained since the diffusion and dispersion of the brine plume are a function of the local circulation regime. These data were used to calculate both near- and far-field concentrations of brine, and may also be used in the design criteria for diffuser port configuration and verification of the plume model. Biological samples were taken to characterize the sites and to predict potential areas of impact with regard to the discharge. This sampling focused on benthic organisms and demersal fish. (DMC)

  15. Preliminary technical data summary for the Defense Waste Processing Facility, Stage 1

    International Nuclear Information System (INIS)

    1980-09-01

    This Preliminary Technical Data Summary presents the technical basis for design of Stage 1 of the Staged Defense Waste Processing Facility (DWPF), a process to efficiently immobilize the radionuclides in Savannah River Plant (SRP) high-level liquid waste. The radionuclides in SRP waste are present in sludge that has settled to the bottom of waste storage tanks and in crystallized salt and salt solution (supernate). Stage 1 of the DWPF receives washed, aluminum dissolved sludge from the waste tank farms and immobilizes it in a borosilicate glass matrix. The supernate is retained in the waste tank farms until completion of Stage 2 of the DWPF at which time it filtered and decontaminated by ion exchange in the Stage 2 facility. The decontaminated supernate is concentrated by evaporation and mixed with cement for burial. The radioactivity removed from the supernate is fixed in borosilicate glass along with the sludge. This document gives flowsheets, material, and curie balances, material and curie balance bases, and other technical data for design of the Stage 1 DWPF

  16. Technical data summary supporting the spent nuclear fuel environmental impact statement, November 1993

    International Nuclear Information System (INIS)

    Geddes, R.L.; Claxton, R.E.; Lengel, J.D.

    1993-11-01

    This report has been compiled by the WSRC Nuclear Materials Processing Division's Planning Section at the request of the Office of Spent Fuel Management and Special Projects (EM-37) to support issuance of the Spent Nuclear Fuel Environmental Impact Statement. Savannah River site data evaluates five programmatic options including open-quotes No Actionclose quotes ranging up to transfer of all DOE responsibility spent fuel to the SRS. For each option, a range of management/disposition scenarios has been examined. Each case summary provides information relative to the technical proposal, technical issues, environmental impacts, and projected costs for a 50 period (to 2044) when it is assumed that the material will be dispositioned from the SRS. It must be recognized that this report was prepared under severe time constraints and contains many simplifications and assumptions. It is highly recommended that significant additional study be performed before basing key decisions upon the data contained in this report. It represents a best effort by a significant group of technical personnel familiar with nuclear materials processing, handlings and storage but it is likely that careful scrutiny will reveal numerous discrepancies and omissions. The bulk of the effort went into defining the engineering approaches necessary to execute the various mission scenarios. Collection and/or calculation of much of the various waste, emission, and utility consumption data, so important to an Environmental Impact Statement, has not been completed at this time

  17. Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 5. Baseline rock properties-granite

    International Nuclear Information System (INIS)

    1978-04-01

    This volume, Y/OWI/TM-36/5, Baseline Rock Properties--Granite, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This report, on the rock properties of typical granites, includes an evaluation of the various test results reported in the literature. Firstly, a literature survey was made in order to obtain a feel for the range of rock properties encountered. Then, granites representative of different geologic ages and from different parts of the United States were selected and studied in further detail. Some of the special characteristics of granite, such as anisotropy, creep and weathering were also investigated. Lastly, intact properties for a typical granite were selected and rock mass properties were derived using appropriate correction factors

  18. Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 7. Baseline rock properties-basalt

    International Nuclear Information System (INIS)

    1978-04-01

    This volume, Y/OWI/TM-36/7 Baseline Rock Properties--Basalt, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This report contains an evaluation of the results of a literature survey to define the rock mass properties of a generic basalt, which could be considered as a geological medium for storing radioactive waste. The general formation and structure of basaltic rocks is described. This is followed by specific descriptions and rock property data for the Dresser Basalt, the Amchitka Island Basalt, the Nevada Test Site Basalt and the Columbia River Group Basalt. Engineering judgment has been used to derive the rock mass properties of a typical basalt from the relevant intact rock property data and the geological information pertaining to structural defects, such as joints and faults

  19. Nagra technical report 14-02, geological basics - Dossier I - Introduction and summary

    International Nuclear Information System (INIS)

    Gautschi, A.; Zuidema, P.

    2014-01-01

    This dossier is the first of a series of eight reports concerning the safety and technical aspects of locations for the disposal of radioactive wastes in Switzerland. It presents an introduction to and a summary of the further seven dossiers on basic geological conditions. Dossier II considers the sediments that can be used along with tectonic considerations, Dossier III takes a look at long-term geological developments and Dossier IV considers the geo-mechanical documentation available. Dossier V looks at hydro-geological considerations. Dossier VI reports on the barrier properties of the proposed host rock sediments and neighbouring rock layers. Dossiers VII takes a look at usage conflicts and Dossier VIII considers the possibilities for the characterisation of the substrates and for the ways in which they can be explored

  20. KBS Annual Report 1983. Including summaries of technical reports issued during 1983

    International Nuclear Information System (INIS)

    1984-06-01

    The purpose of the KBS Annual Report is to inform interested organizations and individuals of the research and development work performed by the division KBS within the Swedish Nuclear Fuel Supply Co (SKBF) on the handling, treatment and final storage of nuclear wastes in Sweden. The Annual Report normally contains a presentation of the legal and organizational situation followed by an account of the progress within different areas of the R and D-work. This account also includes indications of the activities planned for the future. At the end of the report the summaries of 76 technical reports and other publications issued during the year are listed in special appendices. (K.A.E.)

  1. LLNL/YMP Waste Container Fabrication and Closure Project; GFY technical activity summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-10-01

    The Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM) Program is studying Yucca Mountain, Nevada as a suitable site for the first US high-level nuclear waste repository. Lawrence Livermore National Laboratory (LLNL) has the responsibility for designing and developing the waste package for the permanent storage of high-level nuclear waste. This report is a summary of the technical activities for the LLNL/YMP Nuclear Waste Disposal Container Fabrication and Closure Development Project. Candidate welding closure processes were identified in the Phase 1 report. This report discusses Phase 2. Phase 2 of this effort involved laboratory studies to determine the optimum fabrication and closure processes. Because of budget limitations, LLNL narrowed the materials for evaluation in Phase 2 from the original six to four: Alloy 825, CDA 715, CDA 102 (or CDA 122) and CDA 952. Phase 2 studies focused on evaluation of candidate material in conjunction with fabrication and closure processes.

  2. Department of Defense Base Structure Report (A Summary of DOD's Real Property Inventory), Fiscal year 2005 Baseline

    National Research Council Canada - National Science Library

    2005-01-01

    The Base Structure Report represents a consolidated summary of the Services native real property inventories to provide an overall look at the physical infrastructure that makes up the Department of Defense...

  3. Technical data summary: Uranium(IV) production using a large scale electrochemical cell

    International Nuclear Information System (INIS)

    Hsu, T.C.

    1984-05-01

    This Technical Data Summary outlines an electrochemical process to produce U(IV), in the form of uranous nitrate, from U(VI), as uranyl nitrate. U(IV) with hydrazine could then be used as an alternative plutonium reductant to substantially reduce the waste volume from the Purex solvent extraction process. This TDS is divided into three parts. The first part (Chapters I to IV) generally describes the electrochemical production of U(IV). The second part (Chapters V to VII) describes a pilot scale U(IV) production facility that was constructed and operated at an engineering semiworks area of SRP, referred to as TNX. The lst part (Chapter VIII) describes a preliminary design for a full-scale facility that would meet the projected need for U(IV) as a reductant in SRP's separations processes. The preliminary design was described in a Basic Data Summary for the U(IV) production facility, and a Venture Guidance Appraisal (VGA) was prepared from the Basic Data Summary. The VGA for the U(IV) process showed that because of the large capital investment required, this approach to waste reduction was not economically competitive with another alternative that required only modifying the ongoing Purex process at no additional capital cost. However, implementing he U(IV) process as part of an overall canyon renovation, presently scheduled for the 1990's, may be economically attractive. The purpose of this TDS is therefore to bring together the information and experience obtained thus far in the U(IV) program so that a useful body of information will be available to support any future development of this process

  4. Summary of Tiger Team Assessment and Technical Safety Appraisal recurring concerns in the Operations Area

    International Nuclear Information System (INIS)

    1993-01-01

    Fourteen Tiger Team Assessment and eight Technical Safety Appraisal (TSA) final reports have been received and reviewed by the DOE Training Coordination Program during Fiscal Year 1992. These assessments and appraisals included both reactor and non-reactor nuclear facilities in their reports. The Tiger Team Assessments and TSA reports both used TSA performance objectives, and list ''concerns'' as a result of their findings. However, the TSA reports categorized concerns into the following functional areas: (1) Organization and Administration, (2) Radiation Protection, (3) Nuclear Criticality Safety, (4) Occupational Safety, (5) Engineering/Technical Support, (6) Emergency Preparedness, (7) Safety Assessments, (8) Quality Verification, (9) Fire Protection, (10) Environmental Protection, and (11) Energetic Materials Safety. Although these functional areas match most of the TSA performance objectives, not all of the TSA performance objectives are addressed. For example, the TSA reports did not include Training, Maintenance, and Operations as functional areas. Rather, they included concerns that related to these topics throughout the 11 functional areas identified above. For consistency, the Operations concerns that were identified in each of the TSA report functional areas have been included in this summary with the corresponding TSA performance objective

  5. The Agency's Technical Co-operation programme with Madagascar, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $3.5 million of Agency support received, Madagascar ranks 42nd among all recipients of technical assistance in the period 1958 through 1991. More than half of the assistance during the past ten years has been provided in the form of equipment (55%), followed by expert services (32%) and training (13%). With a share of 69%, the Technical Assistance and Co-operation Fund has provided more than two-thirds of the total resources available, while 29% were made available through UNDP and 2% through assistance in kind. Extrabudgetary contributions accounted for less than one per cent. With regard to project disbursements during the past ten years, by sector, by far the largest area has been nuclear raw materials (66%), followed by nuclear physics and chemistry (18%). Only small shares have gone to nuclear safety (7%), agriculture (5%) and nuclear engineering and technology (4%)

  6. The Agency's Technical Co-operation programme with Sudan, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $5.7 million of Agency support received, Sudan ranks 31st among all recipients of technical assistance in the period 1958 through 1991. Over the past ten years, almost equal shares of this assistance were provided in the form of equipment (46%) and training (42%), and only a small percentage was provided in the form of expert services (12%). The best part of the resources was made available through the Technical Assistance and Co-operation Fund (77%), while in-kind and extrabudgetary contributions account for 13% and 10% of the resources, respectively. With regard to project disbursement during the past ten years, by sector, the two largest areas have been general atomic energy development (37%) and agriculture (21%), followed by nuclear medicine (14%). Smaller shares (6% each) have gone to nuclear physics and chemistry, nuclear engineering and technology, hydrology, and nuclear safety

  7. The Agency's Technical Co-operation programme with Peru, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $12.6 million of Agency support received, Peru ranks 4th among all recipients of technical assistance in the period 1958 - 1991, whereby it ranked as high as 2nd in each of the four years 1982 through 1985. More than half of the assistance during the past ten years has been provided in the form of equipment (59%), followed by expert services (29%) and training (12%). Forty-five per cent of the resources were provided by the Technical Assistance and Co-operation Fund, while 29% of the resources were made available through extrabudgetary contributions, and 21% by UNDP. The remaining 5% were provided in kind. With regard to project disbursement by sector, the largest areas have been agriculture (27%), general atomic energy development (17%), nuclear raw materials (14%), nuclear medicine (12%) and industry and hydrology (11%). Nuclear safety, nuclear engineering and technology, and nuclear physics and chemistry have each received less than ten per cent of the assistance provided

  8. The Agency's Technical Co-operation programme with Brazil, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $17 million of Agency support received, Brazil ranks 2nd among all recipients of technical assistance during the period 1958 through 1991. Over half of the assistance received during the past ten years has been provided in the form of equipment (51%), complemented by expert services (34%) and training (15%). Almost two-thirds of the funds were made available through the Technical Assistance and Co-operation Fund (63%), the rest was provided through extrabudgetary contributions (30%), assistance in kind (4%) and UNDP (3%). With regard to total disbursements - by sector - under those projects that were operational during the period 1982 through November 1992, the three major areas have been: general atomic energy development (47%), nuclear safety (22%) and agriculture (13%). During the same period, the country has provided experts and training course lectures for a total of 405 assignments, and has hosted 178 fellowships and scientific visits as well as 46 regional and interregional training events with a total of 603 participants

  9. The Agency's Technical Co-operation programme with Cuba, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With almost $8.2 million of Agency support received, Cuba ranks 19th among all recipients of technical assistance in the period 1958 - 1991, whereby it ranked as high as 3rd in 1982 and 4th in 1984. Over three quarters of the assistance during the past ten years has been provided in the form of equipment (81%), followed by expert services (10%) and training (9%). Seventy-one per cent of the resources were made available through the Technical Assistance and Co-operation Fund, while 28% of the resources were provided by UNDP. The remaining 1% was made available through extrabudgetary and in-kind contributions. With regard to project disbursements by sector, the largest areas have been general atomic energy development (36%), agriculture (20%), nuclear physics and chemistry (10%) and nuclear safety (10%). Industry and hydrology, nuclear engineering and technology, and nuclear medicine have each received less than ten per cent of the assistance provided

  10. The Agency's Technical Co-operation programme with Ghana, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $6.5 million of Agency support received, Ghana ranks 29th among all recipients of technical assistance in the period 1958 - 1991. More than half of the assistance during the past ten years has been provided in the form of equipment (53%), followed by training through fellowships and scientific visits (34%) and expert services (13%). Seventy-four per cent of the resources were provided by the Technical Assistance and Co-operation Fund, 13% through assistance in kind, 11% through extrabudgetary contributions, and 2% by UNDP. It should be noted that the share for extrabudgetary contributions includes an amount of $250,000 made available by the Ghanaian Government for the purchase of equipment by the Agency under a funds-in-trust arrangement. With regard to project disbursement by sector, the largest share has gone to agriculture (36%), followed by nuclear physics and chemistry (21%), nuclear medicine (16%), industry and hydrology (14%) and nuclear engineering and technology (9%)

  11. The Agency's Technical Co-operation programme with Egypt, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $22.2 million of Agency support received, Egypt ranks first among all recipients of technical assistance, not only for the period 1958 - 1991, but also held this rank in each of the five years 1982 through 1986 and in 1988. More than half of this assistance has been provided in the form of equipment (57%), followed by expert services (19%), training (17%) and sub-contracts (7%). With 42% and 43%, respectively, the Technical Assistance and Co-operation Fund and extrabudgetary contributions hold almost equal shares in the total resources available, while in-kind assistance accounts for 9% and UNDP for 6% of the resources. With regard to project disbursement during the past ten years, by sector, the two largest areas have been nuclear safety (34%) and agriculture (33%), followed by nuclear engineering and technology (11%). Smaller shares - from 4% to 7% each-- have gone to industry and hydrology, nuclear medicine, nuclear physics and chemistry, and general atomic energy development

  12. Technical data summary supporting the spent nuclear fuel environment impact statement, March 1994

    International Nuclear Information System (INIS)

    Geddes, R.L.; Claxton, R.E.; Lengel, J.D.

    1994-03-01

    This report has been compiled by the WSRC Nuclear Materials Processing Division's Planning Section at the request of the Office of Spent Fuel Management and Special Projects (EM-37) to support issuance of the Spent Nuclear Fuel Environmental Impact Statement. Savannah River Site input data evaluates five programmatic options (including open-quotes No Actionclose quotes) ranging up to transfer of all DOE responsibility spent fuel to the SRS. For each option, a range of management/disposition scenarios has been examined. Each case summary provides information relative to the technical proposal, technical issues, environmental impacts, and projected costs for a forty year period (FY-35) when it is assumed that the material will be dispositioned from the SRS. The original issue of the report which was prepared under severe time constraints contained many simplifications and assumptions. Although the revisions have corrected some of the shortcomings of the original report, it is still highly recommended that significant additional study be performed before basing key decisions upon the data contained in this report. The data represents the best effort by a significant group of technical personnel familiar with nuclear materials processing, handling, and storage; but it is likely that careful scrutiny will reveal numerous discrepancies, inconsistencies and omissions. Nor does this report attempt to analyze every potential disposal pathway, but probably establishes the bounds for the most of the viable pathways. The bulk of the effort went into defining the engineering approaches necessary to execute the various mission scenarios which were changed since the last revision. The decision to limit reprocessing to only SRS aluminum clad required a major alteration of the TDS. Collection and/or calculation of much of the various waste, emission, and utility consumption data, so important to an EIS, has been updated since the last revision, but not thoroughly completed

  13. Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 6. Baseline rock properties-shale

    International Nuclear Information System (INIS)

    1978-04-01

    This volume, Y/OWI/TM36/6 Baseline Rock Properties--Shale, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. The report is a result of a literature survey of the rock properties of shales occurring in the United States. Firstly, data were collected from a wide variety of sources in order to obtain a feel for the range of properties encountered. Secondly, some typical shales were selected for detailed review and these are written up as separate chapters in this report. Owing to the wide variability in lithology and properties of shales occurring in the United States, it became necessary to focus the study on consolidated illite shales. Using the specific information already generated, a consistent set of intact properties for a typical, consolidated illite shale was obtained. Correction factors, largely based on geological considerations, were then applied to the intact data in order to yield typical rock mass properties for this type of shale. Lastly, excavation problems in shale formations were reviewed and three tunnel jobs were written up as case histories

  14. Eleventh annual U.S. DOE low-level radioactive waste management conference: Executive summary, opening plenary, technical session summaries, and attendees

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-01-01

    The conference consisted of ten technical sessions, with three sessions running simultaneously each day. Session topics included: regulatory updates; performance assessment;understanding remedial action efforts; low-level waste strategy and planning (Nuclear Energy); low-level waste strategy and planning (Defense); compliance monitoring; decontamination and decommissioning; waste characterization; waste reduction and minimization; and prototype licensing application workshop. Summaries are presented for each of these sessions.

  15. Study of tunnelling through water-bearing fracture zones. Baseline study on technical issues with NE-1 as reference

    International Nuclear Information System (INIS)

    Yanting Chang; Swindell, Robert; Bogdanoff, Ingvar; Lindstroem, Beatrice; Termen, Jens; Starsec, Peter

    2005-04-01

    The Swedish Nuclear Fuel and Waste Management Co (SKB) is responsible for the management of Sweden's nuclear waste. SKB is investigating various designs for the construction of an underground deep repository for spent nuclear fuel at 500-600 m depths. For the construction of an access tunnel for such a deep repository, the possibility of encountering a water-bearing fracture zone cannot be discounted. Such a zone named NE-1 (deformation zone in accordance to SKB's terminology) was encountered during the construction of the Aespoe Hard Rock Laboratory (HRL) and difficulties with large water inflows were reported. With the aim to assess the feasibility of different technical solutions, SKB commissioned a baseline study into the passage of an access tunnel through a water-bearing fracture zone at three different depths (200 m, 400 m and 600 m). The objectives of this baseline study are to: Increase the knowledge of possible technical solutions for tunnelling through water-bearing fractures zones with the characteristics of the brittle deformation zone NE-1 at different depths, namely 200, 400 and 600 metres; Form a reference document to assist the engineering design and construction work for the passage through such a water-bearing fracture zone; To highlight the engineering parameters that should be obtained to facilitate design for the passage through water-bearing fracture zones.The study has been carried out in the following five stages: A. Compilation of the relevant data for deformation zone NE-1; B. Problem identification and proposal of technical solutions; C. Identification of hazards to be involved in the tunnel excavation; D. Recommendations and conclusions for further investigations; E. Documentation of the results in a final report. The analyses will be expressed in statistical/probabilistic terms where appropriate. In order to specify the precondition that will be valid for this study, a descriptive model of the water-bearing fracture zone is established

  16. Study of tunnelling through water-bearing fracture zones. Baseline study on technical issues with NE-1 as reference

    Energy Technology Data Exchange (ETDEWEB)

    Yanting Chang; Swindell, Robert; Bogdanoff, Ingvar; Lindstroem, Beatrice; Termen, Jens [WSP Sweden, Stockholm (Sweden) ; Starsec, Peter [SGI, Linkoeping (Sweden)

    2005-04-01

    The Swedish Nuclear Fuel and Waste Management Co (SKB) is responsible for the management of Sweden's nuclear waste. SKB is investigating various designs for the construction of an underground deep repository for spent nuclear fuel at 500-600 m depths. For the construction of an access tunnel for such a deep repository, the possibility of encountering a water-bearing fracture zone cannot be discounted. Such a zone named NE-1 (deformation zone in accordance to SKB's terminology) was encountered during the construction of the Aespoe Hard Rock Laboratory (HRL) and difficulties with large water inflows were reported. With the aim to assess the feasibility of different technical solutions, SKB commissioned a baseline study into the passage of an access tunnel through a water-bearing fracture zone at three different depths (200 m, 400 m and 600 m). The objectives of this baseline study are to: Increase the knowledge of possible technical solutions for tunnelling through water-bearing fractures zones with the characteristics of the brittle deformation zone NE-1 at different depths, namely 200, 400 and 600 metres; Form a reference document to assist the engineering design and construction work for the passage through such a water-bearing fracture zone; To highlight the engineering parameters that should be obtained to facilitate design for the passage through water-bearing fracture zones.The study has been carried out in the following five stages: A. Compilation of the relevant data for deformation zone NE-1; B. Problem identification and proposal of technical solutions; C. Identification of hazards to be involved in the tunnel excavation; D. Recommendations and conclusions for further investigations; E. Documentation of the results in a final report. The analyses will be expressed in statistical/probabilistic terms where appropriate. In order to specify the precondition that will be valid for this study, a descriptive model of the water-bearing fracture zone is

  17. Magnetic Fusion Energy Program. Volume I. Introduction, technical summaries, list of publications, etc., Appendices A-K. Annual report

    International Nuclear Information System (INIS)

    Aamodt, R.E.; Byrne, R.N.; Catto, P.J.

    1979-12-01

    An abstract was prepared for the progress summary on transport theory for open and closed magnetic configurations. Seven abstracts were prepared for included appendices of more detailed work on individual devices. Also included is a list of publications, technical presentations, and DOE program contributions

  18. Mixed Methods in Education Research. IES Technical Working Group Meeting. Meeting Summary (Washington, DC, May 29, 2015)

    Science.gov (United States)

    Institute of Education Sciences, 2015

    2015-01-01

    This meeting summary is organized into two major sections. The first section captures the individual contribution of meeting participants, including both Institute of Education Sciences (IES) staff and the invited technical working group members. The second section captures themes that arose during the group discussions, which were organized…

  19. The International Linear Collider Technical Design Report - Volume 1: Executive Summary

    Energy Technology Data Exchange (ETDEWEB)

    Behnke, Ties [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Brau, James E. [Univ. of Oregon, Eugene, OR (United States); Foster, Brian [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Fuster, Juan [Univ. of Valencia (Spain); Harrison, Mike [Brookhaven National Lab. (BNL), Upton, NY (United States); Paterson, James McEwan [SLAC National Accelerator Lab., Menlo Park, CA (United States); Peskin, Michael [SLAC National Accelerator Lab., Menlo Park, CA (United States); Stanitzki, Marcel [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Walker, Nicholas [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Yamamoto, Hitoshi [Tohoku Univ., Sendai (Japan)

    2013-06-26

    The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.

  20. SKB annual report 1993. Including summaries of technical reports issued during 1993

    International Nuclear Information System (INIS)

    1994-05-01

    This is the annual report on the activities of the Swedish Nuclear and Waste Management Co., SKB. It contains in part I an overview of SKB activities in different fields. Part II gives a description of the research and development work on nuclear waste disposal performed during 1993. Lectures and publications during 1993 as well as reports issued in the SKB technical series are listed in part III. Part IV contains the summaries of all technical reports issued during 1993. SKB is the owner of CLAB, the Central Facility for Interim Storage of Spent Nuclear Fuel, located at Oskarshamn. CLAB was taken into operation in July 1985 and to the end of 1993 in total 1 885 tonnes of spent fuel (measured as uranium) have been received. Transportation from the nuclear sites to CLAB is made by a special ship, M/S Sigyn. At Forsmark the final repository for Radioactive Waste - SFR - was taken into operation in April 1988. The repository is situated in crystalline rock under the Baltic Sea. At the end of 1993 a total of 13 000 m 3 of waste have been deposited in SFR. SKB is in charge of a comprehensive research and development programme on geological disposal of nuclear waste. Some of the main areas for SKB research are: Groundwater movements; Bedrock stability; Groundwater chemistry and nuclide migration; Methods and instruments for in situ characterization of crystalline bedrock; Characterization and leaching of spent nuclear fuel; Properties of bentonite for buffer, backfilling and sealing; Radionuclide transport in biosphere and dose evaluations; Development of performance and safety assessment methodology and assessment models; Construction of an underground research laboratory

  1. Decontaminated salt disposal as saltcrete in a landfill. Technical data summary

    International Nuclear Information System (INIS)

    1982-01-01

    This technical data summary presents a reference process for immobilizing decontaminated salt solution from the 200-Area waste storage tanks with cement, and disposing of the final waste material (called saltcrete) by burial in trenches. The saltcrete will be protected from leaching by clay and will be placed at least 3 meters above the historic high water table and beneath at least 5 meters of soil overburden. The decontaminated salt solution is a waste material which remains after the bulk of the radionuclides have been removed from waste tank supernate. This removal is effected by contacting the waste supernate with sodium tetraphenyl boron (Na-TPB) and sodium titanate (NaTi 2 O 5 H). These materials remove (by precipitation) most of the 137 Cs and 90 Sr as well as many other radioactive and non-radioactive elements. These precipitates, along with many other sludges which reside in the HLW tanks will be incorporated in borosilicate glass for eventual disposal in a geologic repository. An ion exchange process will also be used for removal of 99 Tc. The decontaminated salt solution has sufficiently low levels of radioactivity that it can be disposed of on-site. The scope of the curent effort is to describe a process for blending decontaminated salt solution with cement to form a saltcrete product which has dimensional stability and relatively low leachability. The process is to be capable of solidifying 10 gpm of supernate. About 100 million gallons of salt solution is to be solidified

  2. The Agency's Technical Co-operation programme with Argentina, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $7.5 million of Agency support received, Argentina ranks 22nd among all recipients of technical assistance during the period 1958 through 1991. Forty-six per cent of the assistance received during the past ten years has been provided in the form of equipment, complemented by expert services (40%) and training (14%). The largest share of the resources was made available by UNDP (87%), and only small shares were provided through the TACF (12%) and assistance in kind (less than 1%). With regard to total disbursements - by sector - under those projects that were operational during the period 1982 through mid-December 1992, by far the largest area has been nuclear engineering and technology (91%), while only very small shares went to nuclear safety (4%), industry and hydrology (3%) and agriculture (2%). During the same period, the country has provided experts and training course lectures for a total of 601 assignments, and has hosted 153 fellowships and scientific visits as well as 42 regional and interregional training courses with a total of 568 participants

  3. Summary

    International Nuclear Information System (INIS)

    2004-01-01

    The fourth workshop of the OECD/NEA Forum on Stakeholder Confidence (FSC) was hosted by ONDRAF/NIRAS, the Belgian Agency for Radioactive Waste Management and enriched fissile materials. The central theme of the workshop was ''Dealing with interests, values and knowledge in managing risk''within the Belgian context of local partnerships for the long term management of low-level, short-lived radioactive waste. The four-day workshop started with a half-day session in Brussels giving a general introduction on the Belgian context and the local partnership methodology. This was followed by community visits to three local partnerships, PaLoFF in Fleurus-Farciennes, MONA in Mol, and STOLA in Dessel. After the visits, the workshop continued with two full-day sessions in Brussels. One hundred and nineteen registered participants, representing 13 countries, attended the workshop or participated in the community visits. About two thirds were Belgian stakeholders; the remainder came from FSC member organisations. The participants included representatives of municipal governments, civil society organisations, government agencies, industrial companies, the media, and international organisations as well as private citizens, consultants and academics. This Executive Summary gives an overview of the presentations and discussions that took place at the workshop and the community visits. The structure of the Executive Summary follows the structure of the workshop itself. Complementary to this Executive Summary and also provided with this document, is a NEA Secretariat's reflection aiming to place the main lessons of the workshop into an international perspective. (author)

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

    International Nuclear Information System (INIS)

    1995-11-01

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

  5. The international linear collider. Technical design report. Vol. 1. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    Behnke, Ties; Brau, James E.; Foster, Brian; Fuster, Juan; Harrison, Mike; McEwan Paterson, James; Peskin, Michael; Stanitzki, Marcel; Walker, Nicholas; Yamamoto, Hitoshi (eds.)

    2013-07-01

    A review is given about the planned International Linear Collider. Especially described are the technical design, the accelerator layout and design, the R and D during the technical design phase, and the detectors. (HSI)

  6. The international linear collider. Technical design report. Vol. 1. Executive summary

    International Nuclear Information System (INIS)

    Behnke, Ties; Brau, James E.; Foster, Brian; Fuster, Juan; Harrison, Mike; McEwan Paterson, James; Peskin, Michael; Stanitzki, Marcel; Walker, Nicholas; Yamamoto, Hitoshi

    2013-01-01

    A review is given about the planned International Linear Collider. Especially described are the technical design, the accelerator layout and design, the R and D during the technical design phase, and the detectors. (HSI)

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

    International Nuclear Information System (INIS)

    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 ampersand M) until the facilities are included in the Decontamination and Decommissioning (D ampersand 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 ampersand 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. Summary of technical information and agreements from Nuclear Management and Resources Council industry reports addressing license renewal

    International Nuclear Information System (INIS)

    Regan, C.; Lee, S.

    1996-10-01

    In about 1990, the Nuclear Management and Resources Council (NUMARC) submitted for NRC review ten industry reports (IRs) addressing aging issues associated with specific structures and components of nuclear power plants ad one IR addressing the screening methodology for integrated plant assessment. The NRC staff had been reviewing the ten NUMARC IRs; their comments on each IR and NUMARC responses to the comments have been compiled as public documents. This report provides a brief summary of the technical information and NUMARC/NRC agreements from the ten IRs, except for the Cable License Renewal IR. The technical information and agreements documented herein represent the status of the NRC staffs review when the NRC staff and industry resources were redirected to address rule implementation issues. The NRC staff plans to incorporate appropriate technical information and agreements into the draft standard review plan for license renewal

  9. Baseline assessment of benthic communities of the Flower Garden Banks (2010 - 2013) using technical diving operations: 2011

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The proposed work develop baseline information on fish and benthic communities within the Flower Garden Banks National Marine Sanctuary (FGBNMS). Surveys will employ...

  10. Baseline assessment of benthic communities of the Flower Garden Banks (2010 - 2013) using technical diving operations: 2011

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The work developed baseline information on fish and benthic communities within the Flower Garden Banks National Marine Sanctuary (FGBNMS). Surveys employed diving,...

  11. Baseline assessment of fish communities of the Flower Garden Banks (2010 - 2013) using technical diving operations: 2011

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The proposed work develop baseline information on fish and benthic communities within the Flower Garden Banks National Marine Sanctuary (FGBNMS). Surveys will employ...

  12. High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Executive summary: Volume 1

    International Nuclear Information System (INIS)

    Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B.

    1995-06-01

    The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer software used in the safety systems of nuclear power plants. The framework for the work consisted of the following software development and assurance activities: requirements specification; design; coding; verification and validation, including static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire range of software life-cycle activities; the assessment of the technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary, includes an overview of the framework and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; Volume 2 is the main report

  13. Summary

    International Nuclear Information System (INIS)

    1982-01-01

    The International Tokamak Reactor (INTOR) Workshop is an unique collaborative effort among Euratom, Japan, the USA and the USSR, under the auspices of the IAEA, to assess, define, design, construct and operate the next major experiment in the World Tokamak Program beyond the TFTR, JET, JT-60, T-15 generation. During the Zero-Phase (1979), a technical data base assessment was performed, leading to a positive assessment of feasibility. During Phase-1 (1/80-6/81), a conceptual design was developed to define the concept. The programmatic objectives are that INTOR should: (1) be the maximum reasonable step beyond the TFTR, JET, JT-60, T-15 generation of tokamaks, (2) demonstrate the plasma performance required for tokamak DEMOs, (3) test the development and integration into a reactor system of those technologies required for a DEMO, (4) serve as a test facility for blanket, tritium production, materials, and plasma engineering technology, (5) test fusion reactor component reliability, (6) test the maintainability of a fusion reactor, and (7) test the factors affecting the reliability, safety and environmental acceptability of a fusion reactor. A conceptual design has been developed to define a device which is consistent with these objectives. The design concept could, with a reasonable degree of confidence, be developed into a workable engineering design of a tokamak that met the performance objectives of INTOR. There is some margin in the design to allow for uncertainty. While design solutions have been found for all of the critical issues, the overall design may not yet be optimal

  14. Summary

    International Nuclear Information System (INIS)

    Roehlig, Klaus-Juergen

    2014-01-01

    Document available in abstract form only. Full text follows: During the five sessions of the workshop, much insight has been gained in a variety of issues and challenges that national programmes will encounter as they approach the construction phase of deep geologic repositories as well as their plans to address and resolve these issues. Due to the wide range of participating programmes and due to the different phases of repository development represented, the information presented at the workshop ranged from general and generic questions to specific technical, managerial, administrative, legal, regulatory and procedural issues. Although many issues still awaiting their resolutions, it can be observed that there were joint views amongst the participants with respect to the nature and specificities of these issues. These include: - the need for flexibility (within a so-called safety envelope) when projects evolve over time, - the need to address targets could be very difficult in nature and in some cases may compete with each other when developing and optimising repository systems, - the central role of management with regard to developing adequate professional attitudes and an appropriate safety culture, taking into account the various professional disciplines involved, - the need for integrating different legal and regulatory fields, often addressed by different authorities, and the question of a 'leading regulator'; - the technical challenge of conceptualising parallel processes such as excavation in parts of a repository and emplacement in others and the need to fulfil related safety requirements (mining and occupational, radiation protection etc.), - monitoring may have different roles in different phases of repository development, or - the outstanding role of the safety case prepared in advance to operation (waste emplacement) compared to the cases prepared at other stages of repository development, and the need to act accordingly in the regulatory

  15. The Agency's technical co-operation programme with Syrian Arab Republic 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Syrian Arab Republic carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  16. The Agency's technical co-operation programme with Cote d'Ivoire 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in Cote d'Ivoire carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  17. The Agency's technical co-operation programme with the People's Republic of China 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in the People's Republic of China carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  18. IAEA International Database on Irradiated Nuclear Graphite Properties. Summary report of consultants' meeting. 12. meeting of the Technical Steering Committee

    International Nuclear Information System (INIS)

    Chung, H.K.; Wickham, A.J.

    2010-02-01

    The 12th Meeting of the Technical Steering Committee for the International Database on Irradiated Nuclear Graphite Properties was held on 12-13 November 2009 at the IAEA Headquarters, Vienna, Austria. All discussions, recommendations and actions of this Consultants' Meeting are recorded in this report. The purposes of the meeting were to review the matters and actions identified in the previous meeting, undertake a review of the current status of the database, and make recommendations for action over the next year. This report contains the status of the identified actions as well as a summary of the recommendations on enhancements to the database. (author)

  19. The Agency's technical co-operation programme with the Republic of Korea 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in the Republic of Korea carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  20. The Agency's technical co-operation programme with the Islamic Republic of Iran 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in the Islamic Republic of Iran carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  1. The Agency's technical co-operation programme with the Islamic Republic of Iran 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in the Islamic Republic of Iran carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  2. The Agency's technical co-operation programme with the United Arab Emirates 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in the United Arab Emirates carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  3. The Agency's Technical Co-operation programme with Cote d'Ivoire, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $1.7 million of Agency support received, Cote d'Ivoire ranks 60th among all recipients of technical assistance in the period 1958 through 1991. Over half of the assistance received during the past ten years has been in the form of equipment (59%), complemented by expert services (26%) and training (15%). The best part of the resources was provided by the Technical Assistance and Co-operation Fund (91%), the remainder was made available through extrabudgetary contributions (7%) and through assistance in kind (2%). During the past ten years, project activities - and disbursements - have concentrated exclusively on three major areas: agriculture (59%), general atomic energy development (30%) and nuclear safety (11%)

  4. The Agency's Technical Co-operation programme with the United Republic of Tanzania, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $ 3.4 million of Agency support received, the United Republic of Tanzania ranks 44th among all recipients of technical assistance in the period 1958 - 1991. Almost half of the assistance during the past ten years has been provided in the form of equipment (49%), followed by training through fellowships and scientific visits (29%) and expert services (22%). Ninety-two per cent of the resources were provided by the Technical Assistance and Co-operation Fund, the rest was made available through assistance in kind (5%) and through extrabudgetary contributions (3%). With regard to project disbursement by sector, by far the largest share has gone to agriculture (48%), followed by nuclear physics (20%), nuclear safety (17%) and nuclear medicine (11%)

  5. International Linear Collider Technical Design Report (Volumes 1 through 4)

    Energy Technology Data Exchange (ETDEWEB)

    Harrison M.

    2013-03-27

    The design report consists of four volumes: Volume 1, Executive Summary; Volume 2, Physics; Volume 3, Accelerator (Part I, R and D in the Technical Design Phase, and Part II, Baseline Design); and Volume 4, Detectors.

  6. [Fuel substitution of vehicles by natural gas: Summaries of four final technical reports

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-01

    This report contains summary information on three meetings and highlights of a fourth meeting held by the Society of Automotive Engineers on natural gas fueled vehicles. The meetings covered the following: Natural gas engine and vehicle technology; Safety aspects of alternately fueled vehicles; Catalysts and emission control--Meeting the legislative standards; and LNG--Strengthening the links.

  7. Technical committee meeting on aerosol formation, vapour deposits and sodium vapour trapping. Summary report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-01-01

    The papers presented at the LMFBR meeting on aerosol formation covered the following four main topics: theoretical studies on aerosol behaviour and comparison with experimental results; techniques for measurement of aerosols; techniques for trapping sodium vapour and aerosols in gas circuits; design of components having to cope with aerosol deposits. The resulting summaries, conclusions and recommendations which were were agreed upon are presented.

  8. Three Mile Island technical information and examination program instrumentation and electrical summary report

    International Nuclear Information System (INIS)

    Meininger, R.D.

    1985-07-01

    This report summarizes the investigations on instrumentation and electrical systems that were subjected to a loss-of-coolant accident environment during and following the accident at Three Mile Island Unit-2 (TMI-2) on March 28, 1979. The report is a summary of information previously published in GEND-INF reports, plus current knowledge of the investigators

  9. 75 FR 82241 - Technical Correction: Completion of Entry and Entry Summary-Declaration of Value

    Science.gov (United States)

    2010-12-30

    ... Entry Summary-- Declaration of Value AGENCY: Customs and Border Protection, Department of Homeland... manner by which the declared transaction value on imported merchandise was determined. This requirement... whether the transaction value of imported merchandise is determined on the basis of the price paid by the...

  10. Technical committee meeting on aerosol formation, vapour deposits and sodium vapour trapping. Summary report

    International Nuclear Information System (INIS)

    1977-01-01

    The papers presented at the LMFBR meeting on aerosol formation covered the following four main topics: theoretical studies on aerosol behaviour and comparison with experimental results; techniques for measurement of aerosols; techniques for trapping sodium vapour and aerosols in gas circuits; design of components having to cope with aerosol deposits. The resulting summaries, conclusions and recommendations which were were agreed upon are presented

  11. Task Order 22 – Engineering and Technical Support, Deep Borehole Field Test. AREVA Summary Review Report

    Energy Technology Data Exchange (ETDEWEB)

    Denton, Mark A. [AREVA Federal Services, Charlotte, NC (United States)

    2016-01-19

    Under Task Order 22 of the industry Advisory and Assistance Services (A&AS) Contract to the Department of Energy (DOE) DE-NE0000291, AREVA has been tasked with providing assistance with engineering, analysis, cost estimating, and design support of a system for disposal of radioactive wastes in deep boreholes (without the use of radioactive waste). As part of this task order, AREVA was requested, through a letter of technical direction, to evaluate Sandia National Laboratory’s (SNL’s) waste package borehole emplacement system concept recommendation using input from DOE and SNL. This summary review report (SRR) documents this evaluation, with its focus on the primary input document titled: “Deep Borehole Field Test Specifications/M2FT-15SN0817091” Rev. 1 [1], hereafter referred to as the “M2 report.” The M2 report focuses on the conceptual design development for the Deep Borehole Field Test (DBFT), mainly the test waste packages (WPs) and the system for demonstrating emplacement and retrieval of those packages in the Field Test Borehole (FTB). This SRR follows the same outline as the M2 report, which allows for easy correlation between AREVA’s review comments, discussion, potential proposed alternatives, and path forward with information established in the M2 report. AREVA’s assessment focused on three primary elements of the M2 report: the conceptual design of the WPs proposed for deep borehole disposal (DBD), the mode of emplacement of the WP into DBD, and the conceptual design of the DBFT. AREVA concurs with the M2 report’s selection of the wireline emplacement mode specifically over the drill-string emplacement mode and generically over alternative emplacement modes. Table 5-1 of this SRR compares the pros and cons of each emplacement mode considered viable for DBD. The primary positive characteristics of the wireline emplacement mode include: (1) considered a mature technology; (2) operations are relatively simple; (3) probability of a

  12. Transfer of Air Force technical procurement bid set data to small businesses, using CALS and EDI. Summary report. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-01-10

    This report provides a summary of the Air Force CALS Test Network (AFCTN) Test Report Transfer of Air Force Technical Procurement Bid Set Data to Small Businesses, Using CALS and EDI (AFCTN Test Report 94-034, UCRL-ID-118619). It represents a synthesis of the results, conclusions, and recommendations, as well as a more concise presentation of the issues and strategies as viewed from AFCTN`s perspective. This report documents a test transfer of three Air Force technical procurement bid sets to one large and twelve small businesses, using the Department of Defense (DoD) Continuous Acquisition and Life-cycle Support (CALS) and ANSI ASC X12 Electronic Data Interchange (EDI) standards. The main goal of the test was to evaluate the effectiveness of using CALS technical data within the context of the DoD`s EDI-based standard approach to electronic commerce in procurement, with particular emphasis on receipt and use of the data by small contractors. Air Force procurement data was provided by the Sacramento Air Logistics Center at McClellan Air Force Base; the manufacturing participants were selected from among McClellan`s {open_quote}Blue Ribbon{close_quote} contractors, located throughout the United States. The test was sponsored by the Air Force CALS Test Network, headquartered at Wright-Patterson Air Force Base. The test successfully demonstrated the technical feasibility of including CALS MIL-R-28002 (Raster) engineering data in an EDI Specification/Technical Information transaction set (ANSI ASC X12 841) when issuing electronic requests for quotation to small businesses. In many cases, the data was complete enough for the contractor participant to feel comfortable generating a quote.

  13. Summaries of studies carried out in the NKS/BOK-2 project. Technical report

    International Nuclear Information System (INIS)

    Palsson, S.E.

    2002-12-01

    Summaries of studies carried out in the NKSBOK-2 project, Radiological and Environmental Consequences. The structure of the project as such is described in NKS-64, Radiological and Environmental Consequences - Final Report of the Nordic Nuclear Safety Research Project BOK-2. That report also includes compilations based on the summaries presented in this report. The project was carried out 1998-2001 with participants from all the Nordic countries. Representatives from the Baltic States were also invited to some of the meetings and seminars. The project consisted of work on terrestrial and marine radioecology and had a broad scope in order to enable participation of research groups with various fields of interest. The topics included improving assessment of old and recent fallout, use of radionuclides as tracers in Nordic marine areas, improving assessment of internal doses and use of mass spectrometry in radioecology. This report is a compilation of summaries from each research group, 32 papers in all, and gives references to papers published in scientific journals. Some of the studies have been described previously, at least to some degree, in NKS-70, Proceedings of the 8 th Nordic Seminar on Radioecology, 25-28 February 2001, Rovaniemi, Finland. (au)

  14. 2011 Residential Energy Efficiency Technical Update Meeting Summary Report: Denver, Colorado - August 9-11, 2011

    Energy Technology Data Exchange (ETDEWEB)

    2011-11-01

    This report provides an overview of the U.S. Department of Energy Building America program's Summer 2011 Residential Energy Efficiency Technical Update Meeting. This meeting was held on August 9-11, 2011, in Denver, Colorado, and brought together more than 290 professionals representing organizations with a vested interest in energy efficiency improvements in residential buildings.

  15. Summary of breakout Session F1: F1, decision support systems - technical databases

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    The discussions in breakout session F1 are summarized. The topics discussed include oil properties database, case histories database, technical experts database, sorbents database, dispersants database, equipment inventories, and response information. General comments and concerns were discussed and major research issues outlines

  16. Summary report of the final technical meeting on 'International Reactor Dosimetry File: IRDF-2002'

    International Nuclear Information System (INIS)

    Griffin, Patrick J.; Paviotti-Corcuera, R.

    2003-10-01

    Presentations, recommendations and conclusions of the Final Technical Meeting on 'International Reactor Dosimetry File: IRDF-2002' are summarized in this report. The main aims of this meeting were to discuss scientific and technical matters related to reactor dosimetry and to assign responsibilities for the preparation of the final version of the IRDF- 2002 library and the associated TECDOC. Tasks were assigned and deadlines were agreed. Participants emphasized that accurate and complete nuclear data for reactor dosimetry are essential to improve the assessment accuracies for reactor pressure vessel service lifetimes in nuclear power plants, as well as for other neutron metrology applications such as boron neutron capture therapy, therapeutic use of medical isotopes, nuclear physics measurements, and reactor safety applications. (author)

  17. Summary report of the technical meeting on 'International Reactor Dosimetry File: IRDF-2002'

    International Nuclear Information System (INIS)

    Greenwood, L.R.; Paviotti-Corcuera, R.

    2002-09-01

    This report summarizes the presentations, recommendations and conclusions of the Technical Meeting on 'International Reactor Dosimetry File: IRDF-2002.' The purpose of this meeting was to discuss scientific and technical matters related to the subject and coordinate related tasks. Discussions were held and recommendations were given for the preparation of the files on topics related to: reactions to be included, need for new evaluations or revisions, decay data, radiation damage data, integral testing in benchmark fields, and computer codes to be included. Tasks were assigned and deadlines were set. The participants emphasized that accurate and complete knowledge of nuclear data for reactor dosimetry are essential for improving the accuracy of the reactor pressure vessel service life assessment of nuclear power plants as well as in other neutron metrology applications such as boron neutron capture therapy, therapeutic use of medical isotopes, nuclear physics measurements, and reactor safety applications. (author)

  18. Summary report of a technical meeting on covariances of nuclear reaction data: GANDR project

    International Nuclear Information System (INIS)

    Trkov, A.

    2005-04-01

    Highlights of the technical meeting are given with respect to the detailed study of the feasibility of creating a tool for the Global Assessment of Nuclear Data Requirements (GANDR) based on sensitivity and uncertainty analysis. GANDR was concluded to be fully practical on a modern computer of the desktop class. Participants debated their requirements and formulated recommendations and proposals for implementation. Specific tasks were assigned to participants with an estimated time for their execution. (author)

  19. International Code Centres Network. Summary Report of the 3rd Biennial Technical Meeting

    International Nuclear Information System (INIS)

    Chung, Hyun-Kyung

    2013-07-01

    This report summarizes the proceedings of the third Technical Meeting of the International Code Centres Network held on 6-8 May in 2013. Ten experts from seven member states and four IAEA staff members attended the three-day meeting held at the IAEA Headquarters in Vienna to discuss issues on uncertainty estimates of theoretical atomic and molecular data. The report includes discussions on data issues, meeting conclusions and recommendations for the IAEA Atomic and Molecular Data Unit. (author)

  20. Technical summary of groundwater quality protection program at Savannah River Plant. Volume 1. Site geohydrology, and solid and hazardous wastes

    International Nuclear Information System (INIS)

    Christensen, E.J.; Gordon, D.E.

    1983-12-01

    The program for protecting the quality of groundwater underlying the Savannah River Plant (SRP) is described in this technical summary report. The report is divided into two volumes. Volume I contains a discussion of the general site geohydrology and of both active and inactive sites used for disposal of solid and hazardous wastes. Volume II includes a discussion of radioactive waste disposal. Most information contained in these two volumes is current as of December 1983. The groundwater quality protection program has several elements which, taken collectively, are designed to achieve three major goals. These goals are to evaluate the impact on groundwater quality as a result of SRP operations, to restore or protect groundwater quality by taking corrective action as necessary, and to ensure disposal of waste materials in accordance with regulatory guidelines

  1. Energy from the desert. Very large scale photovoltaic systems: socio-economic, financial, technical and environmental aspects. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    Kurokawa, K.; Ito, M.; Komoto, K.; Vleuten, P. van der; Faiman, D. (eds.)

    2009-05-15

    This executive summary report for the International Energy Agency (IEA) summarises the objectives and concepts of very large scale photovoltaic power generation (VLS-PV) systems and takes a look at the socio-economic, financial and technical aspects involved as well as the environmental impact of such systems. Potential benefits for desert communities, agricultural development and desalination of water are topics that are looked at. The potential of VLS-PV, its energy payback time and CO{sub 2} emission rates are discussed. Case studies for the Sahara and the Gobi Dessert areas are discussed. A VLS-PV roadmap is proposed and scenarios are discussed. Finally, conclusions are drawn and recommendations are made.

  2. SKB Annual Report 1995. Including summaries of Technical Reports issued during 1995

    International Nuclear Information System (INIS)

    1996-05-01

    The annual report covers planning, construction and operation of facilities and systems as well as research, development, demonstration work and information activities. The aim of the program is to start the permanent disposal of spent nuclear fuel around year 2008. Work is undertaken for the development of encapsulation technology on an industrial scale and for design of an encapsulation plant. The siting process for the final repository for spent fuel has started with feasibility studies in a few Swedish municipalities in order to evaluate the potential technical conditions and requirements and the influence on the region. 36 refs, figs

  3. SKB Annual Report 1995. Including summaries of Technical Reports issued during 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-01

    The annual report covers planning, construction and operation of facilities and systems as well as research, development, demonstration work and information activities. The aim of the program is to start the permanent disposal of spent nuclear fuel around year 2008. Work is undertaken for the development of encapsulation technology on an industrial scale and for design of an encapsulation plant. The siting process for the final repository for spent fuel has started with feasibility studies in a few Swedish municipalities in order to evaluate the potential technical conditions and requirements and the influence on the region. 36 refs, figs.

  4. Nuclear Reaction Data and Uncertainties for Radiation Damage. Summary Report of the Technical Meeting

    International Nuclear Information System (INIS)

    Griffin, P.J.; Sjöstrand, H.; Simakov, S.P.

    2016-08-01

    This Meeting was organized to implement the recommendation of the second Research Coordinated Meeting (RCM) of the International Atomic Energy Agency (IAEA) Coordinated Research Project (CRP) “Primary Radiation Damage Cross Sections” to analyse the accuracy and consistency of the radiation damage-relevant nuclear data in the major nuclear data evaluations with the eventual goal of identifying the most reliable data and providing quantitative uncertainty estimates. Participants have considered the status of the primary nuclear data, such as reaction recoils spectra in the latest releases of ENDF, JEFF, JENDL, FENDL, ROSFOND and TENDL nuclear data libraries, and the ways of deriving the damage quantities KERMA, NRT- or arc-dpa and gas production cross sections as well as the recipes for an assessment of their uncertainties. This report contains the contemporary view of the Meeting participants on these issues in the form of a consolidated set of statements, recommendations and individual summaries. (author)

  5. Authorization Decree Application for the creation of the Flamanville-3 Basic Nuclear Installation. Executive Summary of the Technical Review

    International Nuclear Information System (INIS)

    2009-01-01

    On 9 May 2006, Electricite de France (EDF) submitted to the Ministers for Nuclear Safety an authorization decree application for an EPR-type reactor on the site of the Flamanville Nuclear Power Plant (NPP). Article 29 of Act No. 2006-686 of 13 June 2006 on Transparency and Security in the Nuclear Field prescribes that the creation of any basic nuclear installation shall be issued by a decree taken after consultation with the Nuclear Safety Authority (Autorite de surete nucleaire - ASN). The purpose of this report is to provide ASN's Board with a summary of the technical review led by ASN services and carried out by their technical support agencies, namely the IRSN, the GPR and the Standing Nuclear Section of the CCAP between 2001 and 2006. After summing up the conclusions of the review on the safety options of the European Pressurized Reactor (EPR) Project, as carried out between 1993 and 2000, this report describes the process and modalities of the review conducted from 2001 to 2006. Besides providing the opinion of ASN's services on the creation-licence application, it also outlines the further review to be carried out, if the authorization decree is issued. (authors)

  6. TECHNICAL EFFICIENCY AND IMPACT EVALUATION DIFFERENTIALS BETWEEN THE ADOPTERS AND NON-ADOPTERS OF NERICA IN THE SIX BASELINE STATES IN NIGERIA

    Directory of Open Access Journals (Sweden)

    Abiodun Elijah OBAYELU

    2017-04-01

    Full Text Available The study examined the adoption rate of New Rice for Africa (NERICA, technical efficiency differentials of production of these varieties between adopters and non-adopters and the determinants. It further analysed the impact of adoption of NERICA on area cultivated, output, yield, expenditure and total income of rice farmers in the NERICA baseline states in Nigeria. To achieve the objectives, it employed the descriptive statistics, stochastic production frontier and counterfactual outcomes framework of modern evaluation technique (the Local Average Treatment Effect to analyse 621 rice farmers across the six NERICA baseline states in Nigeria in 2012. The findings show that NERICA adopters were more technically efficient than the non-adopters. In addition, adoption of NERICA was found to significantly increase the areas of land cultivated, output, yield, household expenditure, per capita household expenditure and total income among NERICA adopters by 1.2ha (p < 0.01, 1998.2kg (p< 0.01, 191.2kg/ha (p < 0.1, N13,222.63≈$66.4 (p < 0.05, N2,015.6≈$10.1 (p < 0.05 and N145,098.7 ≈$728.0 (p < 0.01 respectively despite their high level of inefficiency (39 percent by the adopters. The positive impact of NERICA adoption on rice yields, poverty status measured by the per capita household expenditure and total farm income of farmers is a clear indication that NERICA has the potential to increase rice productivity, reduce poverty and food insecurity. NERICA adoption rate will rise if more farmers are aware of the varieties in the study. Farmers who had adopted, and government at all levels should therefore intensify their efforts to encourage others rice farmers possibly through the extension agents on the need to grow NERICA varieties so as to increase rice production level, reduce rice importation and ensure a sustainable rice production.

  7. DHS National Technical Nuclear Forensics Program FY 10 Summary Report: Graduate Mentoring Assistance Program (GMAP)

    International Nuclear Information System (INIS)

    Finck, Martha R.

    2011-01-01

    This program provides practical training to DHS graduate fellows in the DOE laboratory complex. It involves coordinating students, their thesis advisors, and their laboratory project mentors in establishing a meaningful program of research which contributes to the graduate student's formation as a member of the nuclear forensics community. The summary report details the student/mentor experience and future plans after the first summer practicum. This program provides practical training to DHS graduate fellows in the DOE laboratory complex. It involves coordinating students, their thesis advisors, and their laboratory project mentors in establishing a meaningful program of research which contributes to the graduate student's formation as a member of the nuclear forensics community. This final written report includes information concerning the overall mentoring experience, including benefits (to the lab, the mentors, and the students), challenges, student research contributions, and lab mentor interactions with students home universities. Idaho National Laboratory hosted two DHS Nuclear Forensics graduate Fellows (nuclear engineering) in summer 2011. Two more Fellows (radiochemistry) are expected to conduct research at the INL under this program starting in 2012. An undergraduate Fellow (nuclear engineering) who worked in summer 2011 at the laboratory is keenly interested in applying for the NF Graduate Fellowship this winter with the aim of returning to INL. In summary, this program appears to have great potential for success in supporting graduate level students who pursue careers in nuclear forensics. This relatively specialized field may not have been an obvious choice for some who have already shown talent in the traditional areas of chemistry or nuclear engineering. The active recruiting for this scholarship program for candidates at universities across the U.S. brings needed visibility to this field. Not only does this program offer critical practical training

  8. IAEA technical meeting: Assess and co-ordinate modelling needs and data providers. Summary report

    International Nuclear Information System (INIS)

    Clark, R.E.H.

    2004-05-01

    This report briefly describes the proceedings, conclusions and recommendations of the Technical Meeting to 'Assess and Co-ordinate Modelling Needs and Data Providers', held on 4-5 December 2003. Eight international experts on atomic and molecular data related to fusion energy research activities participated in the meeting. Each participant reviewed the current status of their own speciality and current lines of research as well as anticipated needs in new data for nuclear fusion energy research. Current CRPs on related topics were reviewed. In light of current research activities and anticipated data needs for fusion, a detailed set of tasks appropriate for a new CRP was developed. This meeting completely fulfilled the specified goals. (author)

  9. Reference data libraries for nuclear applications - ENSDF. Summary report of technical meeting

    International Nuclear Information System (INIS)

    Balabanski, D.; Nichols, A.L.

    2008-11-01

    A Technical Meeting on 'Reference Data Libraries for Nuclear Applications - ENSDF' was held on 10- 11 November 2008 at the IAEA Headquarters, Vienna, Austria. All presentations, discussions and recommendations of this meeting are given in this report. The purpose of the meeting was to review and discuss possible new European input to the ENSDF database (Evaluated Nuclear Structure Data File). These inputs are comprehensive mass-chain evaluations that constitute updated recommendations for the nuclear structure and decay data of nuclides assembled on the basis of mass number. A meeting to address declining European effort was endorsed by the International Nuclear Data Committee in April 2008, and judged as essential in order to balance the share of responsibilities around the world for the maintenance of this important database. (author)

  10. Establishment of A+M Computer Code Network. Summary report of IAEA technical meeting

    International Nuclear Information System (INIS)

    Clark, R.E.H.

    2006-01-01

    Eleven international experts on computational aspects of atomic and molecular data for fusion energy research participated in a technical meeting arranged to discuss the establishment of an A and M Computer Code Network, and held at IAEA Headquarters on 23-25 May 2005. Each participant reviewed the current status of their own speciality and current lines of research, as well as anticipated needs in new data for nuclear fusion energy research. A preliminary method for making these valuable resources more readily available was outlined, and implementation will proceed. Several of the computational tools presented are already available through Internet connections. All the goals of the meeting were achieved, and every participant indicated a desire to see more collaboration and cooperation in fulfilling the A and M data needs for fusion. The discussions, conclusions and recommendations of the meeting are briefly described in this report. (author)

  11. Technical comments by the Swedish delegation to INFCE WG.8 on draft summary reports

    International Nuclear Information System (INIS)

    1979-03-01

    The national papers provide a useful data base for reference. However, due to the variety of system parameters and ground rules used it is difficult to summarize the main findings and particularly to draw general conclusions. For example, we do not recommend using absolute values for natural uranium requirements without further qualification as is done in the Summaries of Sub-group A and B reports. It will always be possible to find options with better figures of merit in this respect at the expense of some other feature such as fuel cost or capital cost. For the same reason we believe that the absolute values of uranium utilization and separative work requirements of tables 2, 6 and 7 in Section A and tables 3.1 A to E, 3.2 A and B, and 3.3 B in Section B should be treated with caution. For absolute values to be meaningful when comparing different reactor systems and fuel cycle options they must be based on uniform optimization procedures, common economic ground rules, and carefully checked calculational methods. This would require a second round effort, which is perhaps beyond the scope of the present INFCE study

  12. Technical Letter Report: Evaluation and Analysis of a Few International Periodic Safety Review Summary Reports

    Energy Technology Data Exchange (ETDEWEB)

    Chopra, Omesh K. [Argonne National Lab., IL (United States). Environmental Science Division; Diercks, Dwight R. [Argonne National Lab., IL (United States). Nuclear Engineering Division; Ma, David Chia-Chiun [Argonne National Lab., IL (United States). Environmental Science Division; Garud, Yogendra S. [Argonne National Lab., IL (United States). Environmental Science Division

    2013-12-17

    and 1988. All of the reports reviewed were the regulator’s assessment of the PSR findings rather than the original PSR report, and all but one were English translations from the original language. In these reviews, it was found that most of the countries base their regulatory guidance to some extent (and often to a large extent) on U.S. design codes and standards, NRC regulatory guidance, and U.S. industry guidance. In addition, many of the observed operational technical issues and OpE events reported for U.S. reactors are also cited in the PSR reports. The PSR reports also identified a number of potential technical material/component performance issues and OpE events that are not commonly reported for U.S. plants.

  13. Technical Letter Report: Evaluation and Analysis of a Few International Periodic Safety Review Summary Reports

    International Nuclear Information System (INIS)

    Chopra, Omesh K.; Diercks, Dwight R.; Ma, David Chia-Chiun; Garud, Yogendra S.

    2013-01-01

    1988. All of the reports reviewed were the regulator's assessment of the PSR findings rather than the original PSR report, and all but one were English translations from the original language. In these reviews, it was found that most of the countries base their regulatory guidance to some extent (and often to a large extent) on U.S. design codes and standards, NRC regulatory guidance, and U.S. industry guidance. In addition, many of the observed operational technical issues and OpE events reported for U.S. reactors are also cited in the PSR reports. The PSR reports also identified a number of potential technical material/component performance issues and OpE events that are not commonly reported for U.S. plants

  14. U.S. oil import vulnerability: The technical replacement capability. Summary

    International Nuclear Information System (INIS)

    1991-10-01

    The report examines the changes that have taken place in world oil markets and the U.S. economy since 1984 and provides revised estimates of the technical oil replacement potential that might be attained in the event of a severe and long lasting cutoff of imported oil. The analysis focuses on technologies that are commercially available today or will be within the next 5 years and that are among the most cost-effective methods for replacing oil use in applicable sectors. It also considers the economic impacts of adopting an aggressive oil replacement strategy in a severe oil emergency. The report presents a variety of policy options that could help accelerate the adoption of oil replacement technologies in preparation for, or in response to, a severe supply disruption, or as part of a long-term national policy to reduce import vulnerability. The report's conclusion that U.S. capability to replace lost oil imports is shrinking should be sobering to those who believe that there are quick and easy technological solutions, or that market forces alone will be sufficient to overcome the substantial economic and social dislocations that could result from a prolonged major oil disruption

  15. Preliminary risk assessment for nuclear waste disposal in space. Volume I. Executive summary of technical report

    International Nuclear Information System (INIS)

    Rice, E.E.; Denning, R.S.; Friedlander, A.L.

    1982-01-01

    Three major conclusions come from this preliminary risk assessment of nuclear waste disposal in space. Preliminary estimates of space disposal risk are low, even with the estimated uncertainty bounds. If calculated mined geologic repository (MGR) release risks remain low, and the EPA requirements continue to be met, then no additional space disposal study effort is warranted. If risks perceived by the public are significant in the acceptance of mined geologic repositories, then consideration of space disposal as an MGR complement is warranted. As a result of this study, the following recommendations are made to NASA and the US DOE: During the continued evaluation of the mined geologic repository risk over the years ahead by DOE, if any significant increase in the calculated health risk is predicted for the MGR, then space disposal should be reevaluated at that time. The risks perceived by the public for the MGR should be evaluated on a broad basis by an independent organization to evaluate acceptance. If, in the future, MGR risks are found to be significant due to some presently unknown technical or social factor, and space disposal is selected as an alternative that may be useful in mitigating the risks, then the following space disposal study activities are recommended: improvement in chemical processing technology for wastes; payload accident response analysis; risk uncertainty analysis for both MGR and space disposal; health risk modeling that includes pathway and dose estimates; space disposal cost modeling; assessment of space disposal perceived (by public) risk benefit; and space systems analysis supporting risk and cost modeling

  16. Explosion-produced ground motion: technical summary with respect to seismic hazards

    Energy Technology Data Exchange (ETDEWEB)

    Rodean, Howard C [Lawrence Radiation Laboratory, University of California, Livermore, CA (United States)

    1970-05-15

    This paper summarizes the present technical knowledge, experimental and theoretical, of how underground nuclear explosions produce seismic motion that may be a hazard at distances measured in tens of kilometers. The effects of explosion yield and rock properties (at the explosion, along the signal propagation path, and at the site where a hazard may exist) on the ground motion are described in detail, and some consideration is given to the relation between ground motion and damage criteria. The energy released in a nuclear explosion is sufficient to vaporize the explosive and to generate an intense shock wave that is propagated outward into the surrounding rock. Part of the energy transported by the shock wave is dissipated in the shocked material. The shock wave strength decreases with distance from the center of the explosion as a consequence of this energy loss and because of geometric (approximately spherical) divergence. The dissipated energy fraction ranges from over 95% (for competent rocks like granite) to over 99% (for crushable, porous rocks like alluvium) of the explosion yield. Therefore, the energy fraction that is radiated in the form of seismic waves ranges from a few percent down to a few tenths of a percent. This is consistent with the observation that explosions in granite produce more severe ground motion than corresponding explosions in alluvium. The effects of explosion yield and rock properties on the frequency spectrum of the seismic source function are demonstrated by both experimental measurements and theoretical analysis. The characteristics of an ideal elastic medium are such that its frequency response is that of a low-pass filter, with its cutoff frequency being a function of the elastic properties of the material and the radius at which the explosion-produced stress wave becomes elastic. There is further frequency- and distance-dependent attenuation (especially of the higher frequencies) of the seismic waves, because rocks are not

  17. Explosion-produced ground motion: technical summary with respect to seismic hazards

    International Nuclear Information System (INIS)

    Rodean, Howard C.

    1970-01-01

    This paper summarizes the present technical knowledge, experimental and theoretical, of how underground nuclear explosions produce seismic motion that may be a hazard at distances measured in tens of kilometers. The effects of explosion yield and rock properties (at the explosion, along the signal propagation path, and at the site where a hazard may exist) on the ground motion are described in detail, and some consideration is given to the relation between ground motion and damage criteria. The energy released in a nuclear explosion is sufficient to vaporize the explosive and to generate an intense shock wave that is propagated outward into the surrounding rock. Part of the energy transported by the shock wave is dissipated in the shocked material. The shock wave strength decreases with distance from the center of the explosion as a consequence of this energy loss and because of geometric (approximately spherical) divergence. The dissipated energy fraction ranges from over 95% (for competent rocks like granite) to over 99% (for crushable, porous rocks like alluvium) of the explosion yield. Therefore, the energy fraction that is radiated in the form of seismic waves ranges from a few percent down to a few tenths of a percent. This is consistent with the observation that explosions in granite produce more severe ground motion than corresponding explosions in alluvium. The effects of explosion yield and rock properties on the frequency spectrum of the seismic source function are demonstrated by both experimental measurements and theoretical analysis. The characteristics of an ideal elastic medium are such that its frequency response is that of a low-pass filter, with its cutoff frequency being a function of the elastic properties of the material and the radius at which the explosion-produced stress wave becomes elastic. There is further frequency- and distance-dependent attenuation (especially of the higher frequencies) of the seismic waves, because rocks are not

  18. Western Canada study of animal health effects associated with exposure to emissions from oil and gas field facilities : technical summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-01-15

    The impact of exposure to emissions from oil and gas field facilities on animal and human health has been a long-standing concern in western Canada. This technical summary presented highlights of the 17 major research appendices of a study examining associations between emissions and important reproductive parameters in beef cattle, including pregnancy rates, frequencies of abortions and stillbirths, and the risk of death among young calves. The effect of exposure to emissions on the respiratory, immune and nervous systems of calves and yearlings was also evaluated. The study was an epidemiological investigation that drew on large blocks of data collected from privately owned cow-calf operations, laboratory analyses of biological samples and samplers from air monitors. Mixed effect regression models were used to investigate whether measures of reproductive, immunological, and pathology outcomes were associated with emissions from the petroleum industry. Appropriate statistical adjustments were made to correct for multiple comparisons following standard statistical practice. An overview of the methods used to analyze the data was presented, as well as an examination of the methods of epidemiology in determining a causal effect, and the limitations of a single study in determining causation with certainty. Information on water quality testing and feeding management and forage testing was provided. 15 tabs., 26 figs.

  19. Western Canada study of animal health effects associated with exposure to emissions from oil and gas field facilities : technical summary

    International Nuclear Information System (INIS)

    2006-01-01

    The impact of exposure to emissions from oil and gas field facilities on animal and human health has been a long-standing concern in western Canada. This technical summary presented highlights of the 17 major research appendices of a study examining associations between emissions and important reproductive parameters in beef cattle, including pregnancy rates, frequencies of abortions and stillbirths, and the risk of death among young calves. The effect of exposure to emissions on the respiratory, immune and nervous systems of calves and yearlings was also evaluated. The study was an epidemiological investigation that drew on large blocks of data collected from privately owned cow-calf operations, laboratory analyses of biological samples and samplers from air monitors. Mixed effect regression models were used to investigate whether measures of reproductive, immunological, and pathology outcomes were associated with emissions from the petroleum industry. Appropriate statistical adjustments were made to correct for multiple comparisons following standard statistical practice. An overview of the methods used to analyze the data was presented, as well as an examination of the methods of epidemiology in determining a causal effect, and the limitations of a single study in determining causation with certainty. Information on water quality testing and feeding management and forage testing was provided. 15 tabs., 26 figs

  20. Socioeconomic Forecasting : [Technical Summary

    Science.gov (United States)

    2012-01-01

    Because the traffic forecasts produced by the Indiana : Statewide Travel Demand Model (ISTDM) are driven by : the demographic and socioeconomic inputs to the model, : particular attention must be given to obtaining the most : accurate demographic and...

  1. Technical Aspects of Atomic and Molecular Data Processing and Exchange, 22nd Meeting of the A+M Data Centres Network. Summary Report of an IAEA Technical Meeting

    International Nuclear Information System (INIS)

    Chung, Hyun-Kyung

    2013-12-01

    This report summarizes the proceedings of the IAEA Technical Meeting on ''Technical Aspects of Atomic and Molecular Data Processing and Exchange'' (22nd Meeting of the A+M Data Centres Network) on 4-6 September 2013. Twelve participants from 8 data centres of 6 Member States attended the three-day meeting held at the IAEA Headquarters in Vienna. The report includes discussions on the data issues, meeting conclusions and recommendations and the abstracts of presentations presented in the meeting. (author)

  2. Co-Chairs’ Summary of Technical Session 3B. Nuclear Forensic Science: Synergies with Other Disciplines I

    International Nuclear Information System (INIS)

    Nizamska, M.; Roger, I.

    2015-01-01

    Scientific disciplines, including radiochemistry, provide a technical foundation for the science of nuclear forensics. In addition, analytical chemistry, pathology and nuclear material measurements all contribute to the technical spectrum encompassing a nuclear forensic capability. Subject matter experts versed in the former production of nuclear material may contribute to improved understanding of process streams of interest to a nuclear forensic examination

  3. Technical Aspects of Atomic and Molecular Data Processing and Exchange, 21. Meeting of the A+M Data Centres Network. Summary Report of an IAEA Technical Meeting

    International Nuclear Information System (INIS)

    Chung, H.-K.

    2011-11-01

    This report summarizes the proceedings of the IAEA Technical Meeting on 'Technical Aspects of Atomic and Molecular Data Processing and Exchange' (21st Meeting of the A+M Data Centres Network) on 7-9 September 2011. Fourteen participants from 12 data centres of 7 Member States and 2 International Organizations attended the three-day meeting held at the IAEA Headquarters in Vienna. The report includes discussions on the data issues, meeting conclusions and recommendations and the abstracts of presentations presented in the meeting. (author)

  4. Technical Aspects of Atomic and Molecular Data Processing and Exchange, 21. Meeting of the A+M Data Centres Network. Summary Report of an IAEA Technical Meeting

    Energy Technology Data Exchange (ETDEWEB)

    Chung, H.-K., E-mail: H.Chung@iaea.org [IAEA, Atomic and Molecular Data Unit, Vienna (Austria)

    2011-11-15

    This report summarizes the proceedings of the IAEA Technical Meeting on 'Technical Aspects of Atomic and Molecular Data Processing and Exchange' (21st Meeting of the A+M Data Centres Network) on 7-9 September 2011. Fourteen participants from 12 data centres of 7 Member States and 2 International Organizations attended the three-day meeting held at the IAEA Headquarters in Vienna. The report includes discussions on the data issues, meeting conclusions and recommendations and the abstracts of presentations presented in the meeting. (author)

  5. Summary report of consultants meeting on IAEA International Database on Irradiated Nuclear Graphite Properties. 11. meeting of the Technical Steering Committee

    International Nuclear Information System (INIS)

    Humbert, D.; Wickham, A.J.

    2009-05-01

    The 11th Meeting of the Technical Steering Committee for the International Database on Irradiated Nuclear Graphite Properties was held on 25-26 March 2009 at the IAEA Headquarters, Vienna, Austria. All discussions, recommendations and actions of this Consultants' Meeting are recorded in this report. The purposes of the meeting were to review the matters and actions identified in the previous meeting, undertake a review of the current status of the database, and make recommendations for action over the next year. This report contains the status of the identified actions as well as a summary of the recommendations on enhancements to the database. (author)

  6. Summary report of consultants' meeting - IAEA International Database on Irradiated Nuclear Graphite Properties. 8th meeting of the Technical Steering Committee

    International Nuclear Information System (INIS)

    Humbert, D.; Wickham, A.J.

    2006-05-01

    The '8th Meeting of the Technical Steering Committee for the International Database on Irradiated Nuclear Graphite Properties' was held on 15-16 March 2006 at the IAEA Headquarters, Vienna, Austria. All discussions, recommendations and actions of this Consultants' Meeting are recorded in this report. The purposes of the meeting were to review the matters and actions identified in the previous meeting, undertake a review of the current status of the database and make recommendations for actions for the next year. This report contains the current status of the identified actions as well as a summary of the recommendations on enhancements to the database. (author)

  7. III Scientific-technical conference. Problems and outlooks for development of chemical and radiochemical control in atomic energetics (Atomenergoanalytics-2005). Summaries of reports

    International Nuclear Information System (INIS)

    2005-01-01

    Summaries of reports of the III Scientific-technical conference: Problems and outlooks for development of chemical and radiochemical control in atomic energetics (Atomenergoanalytics-2005) are presented. The conference performed 20-22 September, 2005, in Sosnovyj Bor. Problems of methodical, instrumental and metrological supply of chemical, radiochemical and radiometric control at active NPP and NPU, modern concepts of construction of automated systems of chemical and radiometric control in the atomic energetics, directions for the decision of questions in organization and conducting of chemical and radiochemical control of water-chemical regimes of NPP and NPU are discussed [ru

  8. Technical Evaluation Summary of the In Situ Vitrification Melt Expulsion at the Oak Ridge National Laboratory on April 21, 1996, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1996-11-01

    This Technical Evaluation Summary of the In Situ Vitrification Melt Expulsion at the Oak Ridge National Laboratory on April 21, 1996, was prepared at the request of the Department of Energy as a supporting reference document for the Final Unusual Occurrence Report to fully explore the probable causes that lead to the subject incident. This document provides the Environmental Restoration Program with the technical information on the performance of the in situ vitrification treatability study operations at ORNL pit 1 up to and including the time of the melt expulsion incident. This document also attempts to diagnose the causes of the melt expulsion event the consequent damages to equipment the radiological impacts of the event, and the equipment design modifications and procedural changes necessary for future safe ISV operations

  9. A baseline and watershed assessment in the Lynx Creek, Brenot Creek, and Portage Creek watersheds near Hudson's Hope, BC : summary report

    International Nuclear Information System (INIS)

    Matscha, G.; Sutherland, D.

    2005-06-01

    This report summarized a baseline monitoring program for the Lynx Creek, Brenot Creek, and Portage Creek watersheds located near Hudson's Hope, British Columbia (BC). The monitoring program was designed to more accurately determine the effects of potential coalbed gas developments in the region, as well as to assess levels of agricultural and forest harvesting, and the impacts of current land use activities on water quantity and quality. Water quality was sampled at 18 sites during 5 different flow regimes, including summer and fall low flows; ice cover; spring run-off; and high flows after a heavy summer rain event. Sample sites were located up and downstream of both forest and agricultural activities. The water samples were analyzed for 70 contaminants including ions, nutrients, metals, hydrocarbons, and hydrocarbon fractions. Results showed that while many analyzed parameters met current BC water quality guidelines, total organic carbon, manganese, cadmium, E. coli, fecal coliforms, and fecal streptococci often exceeded recommended guidelines. Aluminum and cobalt values exceeded drinking water guidelines. The samples also had a slightly alkaline pH and showed high conductance. A multiple barrier approach was recommended to reduce potential risks of contamination from the watersheds. It was concluded that a more refined bacteria source tracking method is needed to determine whether fecal pollution has emanated from human, livestock or wildlife sources. 1 tab., 9 figs

  10. IAEA technical meeting: 13th meeting of the IFRC Subcommittee on Atomic and Molecular Data for Fusion. Summary report

    International Nuclear Information System (INIS)

    Clark, R.E.H.; Peacock, N.J.

    2002-11-01

    This report briefly describes the proceedings, conclusions and recommendations of the 13th Meeting of the Subcommittee on Atomic and Molecular Data for Fusion of the International Fusion Research Council held on 24-25 June, 2002 at the IAEA Headquarters in Vienna Austria. The report includes an Executive Summary of the Subcommittee from this Meeting. (author)

  11. Year 3 Summary Report: Baseline Selenium Monitoring of Agricultural Drains Operated by the Imperial Irrigation District in the Salton Sea Basin

    Science.gov (United States)

    Saiki, Michael K.; Martin, Barbara A.; May, Thomas W.

    2008-01-01

    This report summarizes findings from the third year of a 4-year-long field investigation to document selected baseline environmental conditions in 29 agricultural drains and ponds operated by the Imperial Irrigation District along the southern border of the Salton Sea. Routine water quality and fish species were measured at roughly quarterly intervals from April 2007 to January 2008. The water quality measurements included total suspended solids and total (particulate plus dissolved) selenium. In addition, during April and October 2007, water samples were collected from seven intensively monitored drains for measurement of particulate and dissolved selenium, including inorganic and organic fractions. In addition, sediment, aquatic food chain matrices (particulate organic detritus, filamentous algae, net plankton, and midge [chironomid] larvae), and two fish species (western mosquitofish, Gambusia affinis; and sailfin molly, Poecilia latipinna) were sampled from the seven drains for measurement of total selenium concentrations. The mosquitofish and mollies were intended to serve as surrogates for desert pupfish (Cyprinodon macularius), an endangered species that we were not permitted to take for selenium determinations. Water quality values were typical of surface waters in a hot desert climate. A few drains exhibited brackish, near anoxic conditions especially during the summer and fall when water temperatures occasionally exceeded 30 degrees C. In general, total selenium concentrations in water varied directly with conductivity and inversely with pH. Although desert pupfish were found in several drains, sometimes in relatively high numbers, the fish faunas of most drains and ponds were dominated by nonnative species, especially red shiner (Cyprinella lutrensis), mosquitofish, and mollies. Dissolved selenium in water samples from the seven intensively monitored drains ranged from 0.700 to 24.1 ug/L, with selenate as the major constituent in all samples. Selenium

  12. Summaries of studies carried out in the NKS/BOK-2 project. Technical report[Radiological and environmental consequences

    Energy Technology Data Exchange (ETDEWEB)

    Palsson, S E [Icelandic Radiation Protection Inst., Reykjavik (Iceland)

    2002-12-01

    Summaries of studies carried out in the NKSBOK-2 project, Radiological and Environmental Consequences. The structure of the project as such is described in NKS-64, Radiological and Environmental Consequences - Final Report of the Nordic Nuclear Safety Research Project BOK-2. That report also includes compilations based on the summaries presented in this report. The project was carried out 1998-2001 with participants from all the Nordic countries. Representatives from the Baltic States were also invited to some of the meetings and seminars. The project consisted of work on terrestrial and marine radioecology and had a broad scope in order to enable participation of research groups with various fields of interest. The topics included improving assessment of old and recent fallout, use of radionuclides as tracers in Nordic marine areas, improving assessment of internal doses and use of mass spectrometry in radioecology. This report is a compilation of summaries from each research group, 32 papers in all, and gives references to papers published in scientific journals. Some of the studies have been described previously, at least to some degree, in NKS-70, Proceedings of the 8{sup th} Nordic Seminar on Radioecology, 25-28 February 2001, Rovaniemi, Finland. (au)

  13. Baseline rationing

    DEFF Research Database (Denmark)

    Hougaard, Jens Leth; Moreno-Ternero, Juan D.; Østerdal, Lars Peter Raahave

    The standard problem of adjudicating conflicting claims describes a situation in which a given amount of a divisible good has to be allocated among agents who hold claims against it exceeding the available amount. This paper considers more general rationing problems in which, in addition to claims...... to international protocols for the reduction of greenhouse emissions, or water distribution in drought periods. We define a family of allocation methods for such general rationing problems - called baseline rationing rules - and provide an axiomatic characterization for it. Any baseline rationing rule within...... the family is associated with a standard rule and we show that if the latter obeys some properties reflecting principles of impartiality, priority and solidarity, the former obeys them too....

  14. Technical Design Report for large-scale neutrino detectors prototyping and phased performance assessment in view of a long-baseline oscillation experiment

    CERN Document Server

    De Bonis, I.; Duchesneau, D.; Pessard, H.; Bordoni, S.; Ieva, M.; Lux, T.; Sanchez, F.; Jipa, A.; Lazanu, I.; Calin, M.; Esanu, T.; Ristea, O.; Ristea, C.; Nita, L.; Efthymiopoulos, I.; Nessi, M.; Asfandiyarov, R.; Blondel, A.; Bravar, A.; Cadoux, F.; Haesler, A.; Karadzhov, Y.; Korzenev, A.; Martin, C.; Noah, E.; Ravonel, M.; Rayner, M.; Scantamburlo, E.; Bayes, R.; Soler, F.J.P.; Nuijten, G.A.; Loo, K.; Maalampi, J.; Slupecki, M.; Trzaska, W.H.; Campanelli, M.; Blebea-Apostu, A.M.; Chesneanu, D.; Gomoiu, M.C; Mitrica, B.; Margineanu, R.M.; Stanca, D.L.; Colino, N.; Gil-Botella, I.; Novella, P.; Palomares, C.; Santorelli, R.; Verdugo, A.; Karpikov, I.; Khotjantsev, A.; Kudenko, Y.; Mefodiev, A.; Mineev, O.; Ovsiannikova, T.; Yershov, N.; Enqvist, T.; Kuusiniemi, P.; De La Taille, C.; Dulucq, F.; Martin-Chassard, G.; Andrieu, B.; Dumarchez, J.; Giganti, C.; Levy, J.-M.; Popov, B.; Robert, A.; Agostino, L.; Buizza-Avanzini, M.; Dawson, J.; Franco, D.; Gorodetzky, P.; Kryn, D.; Patzak, T.; Tonazzo, A.; Vannucci, F.; Bésida, O.; Bolognesi, S.; Delbart, A.; Emery, S.; Galymov, V.; Mazzucato, E.; Vasseur, G.; Zito, M.; Bogomilov, M.; Tsenov, R.; Vankova-Kirilova, G.; Friend, M.; Hasegawa, T.; Nakadaira, T.; Sakashita, K.; Zambelli, L.; Autiero, D.; Caiulo, D.; Chaussard, L.; Déclais, Y.; Franco, D.; Marteau, J.; Pennacchio, E.; Bay, F.; Cantini, C.; Crivelli, P.; Epprecht, L.; Gendotti, A.; Di Luise, S.; Horikawa, S.; Murphy, S.; Nikolics, K.; Periale, L.; Regenfus, C.; Rubbia, A.; Sgalaberna, D.; Viant, T.; Wu, S.; Sergiampietri, F.; CERN. Geneva. SPS and PS Experiments Committee; SPSC

    2014-01-01

    In June 2012, an Expression of Interest for a long-baseline experiment (LBNO, CERN-SPSC-EOI-007) has been submitted to the CERN SPSC and is presently under review. LBNO considers three types of neutrino detector technologies: a double-phase liquid argon (LAr) TPC and a magnetised iron detector as far detectors. For the near detector, a high-pressure gas TPC embedded in a calorimeter and a magnet is the baseline design. A mandatory milestone in view of any future long baseline experiment is a concrete prototyping effort towards the envisioned large-scale detectors, and an accompanying campaign of measurements aimed at assessing the systematic errors that will be affecting their intended physics programme. Following an encouraging feedback from 108th SPSC on the technology choices, we have defined as priority the construction and operation of a $6\\times 6\\times 6$m$^3$ (active volume) double-phase liquid argon (DLAr) demonstrator, and a parallel development of the technologies necessary for large magnetised MIN...

  15. IAEA technical committee meeting: 10th meeting of the IFRC subcommittee on atomic and molecular data for fusion. Summary report

    Energy Technology Data Exchange (ETDEWEB)

    Janev, R K

    1999-01-01

    This report describes briefly the proceedings and the conclusions and recommendations of the 10th Meeting of the Subcommittee on Atomic and Molecular Data for Fusion of the International Fusion Research Council held on May 27-28, 1998 at the IAEA Headquarters in Vienna, Austria. The report includes also the Executive Summary of the Subcommittee from this Meeting which was communicated to the IAEA Director General, and is appended with the Report on Activities of IAEA A+M Data Unit for the period July 1996 - May 1998. (author)

  16. IAEA technical committee meeting: 12th meeting of the IFRC Subcommittee on Atomic and Molecular Data for Fusion. Summary report

    Energy Technology Data Exchange (ETDEWEB)

    Clark, R E.H. [International Atomic Energy Agency, Vienna (Austria)

    2000-12-01

    This report briefly describes the proceedings, conclusions and recommendations of the 12th Meeting of the Subcommittee on Atomic and Molecular Data for Fusion of the International Fusion Research Council held on May 8-9, 2000 at the IAEA Headquarters in Vienna Austria. The report includes the Executive Summary of the Subcommittee from this Meeting which was communicated to the IAEA Director General as well as the report on the activities of the IAEA Atomic and Molecular Data Unit for the period June 1999 - May 2000. (author)

  17. IAEA technical committee meeting: 11th meeting of the IFRC subcommittee on atomic and molecular data for fusion. Summary report

    International Nuclear Information System (INIS)

    Janev, R.K.

    1999-05-01

    Brief description of the proceedings, conclusions and recommendations of the 11th Meeting of the Subcommittee on Atomic, Molecular (A+M) and Plasma-Material Interaction (PMI) Data for Fusion of the IAEA International Fusion Research Council (IFRC), held on May 3-4, 1999, at the IAEA Headquarters in Vienna, Austria, is provided. The report includes also the Executive Summary from the meeting and is appended with the Report on Activities of IAEA A+M/PMI Data Unit for the period May 1998 - May 1999. (author)

  18. 14th meeting of the IFRC Subcommittee on Atomic and Molecular Data for Fusion. Summary report of IAEA technical meeting

    International Nuclear Information System (INIS)

    Clark, R.E.H.; Peacock, N.J.

    2006-01-01

    The 14th Meeting of the Subcommittee on Atomic and Molecular Data for Fusion of the International Fusion Research Council was held on 24-25 June 2004, at the IAEA Headquarters in Vienna, Austria. Subcommittee members reviewed the work of the Atomic and Molecular Data Unit over the two-year period from June 2002 to June 2004, and made recommendations that covered the 2005-2006 budget cycle. The proceedings, conclusions and recommendations of the meeting are briefly described in this report, along with a short summary of the activities of the IAEA Atomic and Molecular Data Unit of the Nuclear Data Section from June 2002 to June 2004. (author)

  19. Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 1: Executive summary

    International Nuclear Information System (INIS)

    1996-03-01

    A team of analysts designed and conducted a performance evaluation (PE) to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 1 is an executive summary both of the PE methodology and of the results obtained from the PEs. While this volume briefly reviews the scope and method of analyses, its main objective is to emphasize the important insights and conclusions derived from the conduct of the PEs. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussions of the results for each site

  20. Uncertainty Assessment for Theoretical Atomic and Molecular Scattering Data. Summary Report of a Joint IAEA-ITAMP Technical Meeting

    International Nuclear Information System (INIS)

    Chung, Hyun-Kyung; Bartschat, Klaus; Tennyson, Jonathan; Schultz, David R.

    2014-10-01

    This report summarizes the proceedings of the Joint IAEA-ITAMP Technical Meeting on “Uncertainty Assessment for Theoretical Atomic and Molecular Scattering Data” on 7-9 July 2014. Twenty-five participants from ten Member States and one from the IAEA attended the three-day meeting held at the Harvard-Smithsonian Center for Astrophysics in Cambridge, Massachusetts, USA and hosted by the Institute of Theoretical Atomic, Molecular and Optical Physics (ITAMP). The report includes discussions on the issues of uncertainty estimates for theoretical atomic and molecular scattering data. The abstracts of presentations presented in the meeting are attached in the Appendix. (author)

  1. Peer review panel summary report for technical determination of mixed waste incineration off-gas systems for Rocky Flats

    International Nuclear Information System (INIS)

    1992-01-01

    A Peer Review Panel was convened on September 15-17, 1992 in Boulder, Co. The members of this panel included representatives from DOE, EPA, and DOE contractors along with invited experts in the fields of air pollution control and waste incineration. The primary purpose of this review panel was to make a technical determination of a hold, test and release off gas capture system should be implemented in the proposed RF Pland mixed waste incineration system; or if a state of the art continuous air pollution control and monitoring system should be utilized as the sole off-gas control system. All of the evaluations by the panel were based upon the use of the fluidized bed unit proposed by Rocky Flats and cannot be generalized to other systems

  2. IAEA technical meeting on atomic and plasma-material interaction data for fusion science technology. Summary report

    International Nuclear Information System (INIS)

    Clark, R.E.H.

    2003-10-01

    The proceedings and conclusions of the Technical Meeting on 'Atomic and Plasma- Material Interaction Data for Fusion Science Technology' held in Juelich, Germany on October 28-31 are summarized. During the course of the meetings working groups were formed to review the status of specific areas of atomic, molecular and material physics of relevance to fusion and to make recommendations on data needs in fusion from these areas. The reports of those working groups are summarized and the complete reports included as appendices. This meeting brought together over fifty leading scientists in fusion related data. Results of research in a number of topics were presented and very useful discussions were held. The meeting was extremely successful. (author)

  3. Technical and economic assessment of fluidized-bed-augmented compressed-air energy-storage system. Volume I. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    Giramonti, A.J.; Lessard, R.D.; Merrick, D.; Hobson, M.J.

    1981-09-01

    An energy storage system which could be attractive for future electric utility peak-load applications is a modified gas turbine power system utilizing underground storage of very high pressure air. The compressed air energy storage (CAES) concept involves using off-peak electricity generated from indigenous coal or nuclear sources to compress air, storing the air in large underground facilities, and withdrawing the air during peak-load periods when it would be heated by combustion and expanded through gas turbines to generate power. The attractiveness of the CAES concept is based upon its potential to supply competitively priced peaking energy, to reduce peak-load power plant dependence on petroleum-based fuels, and to provide a means for leveling the utility system load demand. Therefore, a technical and economic assessment of coal-fired fluidized bed (FBC) combustor/compressed air energy storage (FBC/CAES) systems was performed and is described. The conclusions drawn from the FBC/CAES study program are encouraging. They indicate that pressurized FBC/CAES power plants should be technologically feasible, provide good performance, and be economically competitive. Specifically, it is concluded that: coal-fired FBC/CAES systems should be technically feasible in the near future and potentially attractive for peak-load power generation; and an open-bed PFBC/CAES configuration would provide the best candidate for early commercialization. It has relatively low risk combined with moderate cost and reasonable round-trip heat rate. It also has the potential for future growth options which tend to reduce costs and lower fuel consumption.

  4. Radionuclide contaminant analysis of small mammals at Area G, Technical Area 54, 1996 (with cumulative summary for 1994--1996)

    International Nuclear Information System (INIS)

    Biggs, J.R.; Bennett, K.D.; Fresquez, P.R.

    1997-07-01

    Small mammals were sampled at two waste burial sites at Area G, Technical Area (TA) 54 and a control site within the proposed Area G expansion area in 1996 to (1) identify radionuclides that are present within rodent tissues at waste burial sites, (2) to compare the amount of radionuclide uptake by small mammals at waste burial sites to a control site, and (3) to identify the primary mode of contamination to small mammals, either through surface contact or ingestion/inhalation. Three composite samples of approximately five animals per sample were collected at each site. Pelts and carcasses of each animal were separated and analyzed independently. Samples were analyzed for 241 Am, 90 Sr, 238 Pu, 239 Pu, total U, 137 Cs, and 3 H. Higher levels of total U, 241 Am, 238 Pu, and 239 Pu were detected in pelts as compared to the carcasses of small mammals at TA-54. Concentrations of other measured radionuclides in carcasses were nearly equal to or exceeded the mean concentrations in the pelts. Due to low sample sizes in total number of animals captured, statistical analysis to compare site to site could not be conducted. However, mean concentrations of total U, 238 Pu, 239 Pu, and 137 Cs in rodent carcasses were higher at Site 1 than site 2 or the Control Site and 241 Am was higher at Site 2 than Site 1 or the Control Site

  5. Baseline Report on HB2320

    Science.gov (United States)

    State Council of Higher Education for Virginia, 2015

    2015-01-01

    Staff provides this baseline report as a summary of its preliminary considerations and initial research in fulfillment of the requirements of HB2320 from the 2015 session of the General Assembly. Codified as § 23-7.4:7, this legislation compels the Education Secretary and the State Council of Higher Education for Virginia (SCHEV) Director, in…

  6. Use of computational fluid dynamics codes for safety analysis of nuclear reactor systems, including containment. Summary report of a technical meeting

    International Nuclear Information System (INIS)

    2003-11-01

    Safety analysis is an important tool for justifying the safety of nuclear power plants. Typically, this type of analysis is performed by means of system computer codes with one dimensional approximation for modelling real plant systems. However, in the nuclear area there are issues for which traditional treatment using one dimensional system codes is considered inadequate for modelling local flow and heat transfer phenomena. There is therefore increasing interest in the application of three dimensional computational fluid dynamics (CFD) codes as a supplement to or in combination with system codes. There are a number of both commercial (general purpose) CFD codes as well as special codes for nuclear safety applications available. With further progress in safety analysis techniques, the increasing use of CFD codes for nuclear applications is expected. At present, the main objective with respect to CFD codes is generally to improve confidence in the available analysis tools and to achieve a more reliable approach to safety relevant issues. An exchange of views and experience can facilitate and speed up progress in the implementation of this objective. Both the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA) believed that it would be advantageous to provide a forum for such an exchange. Therefore, within the framework of the Working Group on the Analysis and Management of Accidents of the NEA's Committee on the Safety of Nuclear Installations, the IAEA and the NEA agreed to jointly organize the Technical Meeting on the Use of Computational Fluid Dynamics Codes for Safety Analysis of Reactor Systems, including Containment. The meeting was held in Pisa, Italy, from 11 to 14 November 2002. The publication constitutes the report of the Technical Meeting. It includes short summaries of the presentations that were made and of the discussions as well as conclusions and

  7. 324 Building Baseline Radiological Characterization

    International Nuclear Information System (INIS)

    Reeder, R.J.; Cooper, J.C.

    2010-01-01

    This report documents the analysis of radiological data collected as part of the characterization study performed in 1998. The study was performed to create a baseline of the radiological conditions in the 324 Building. A total of 85 technical (100 square centimeter (cm 2 )) smears were collected from the Room 147 hoods, the Shielded Materials Facility (SMF), and the Radiochemical Engineering Cells (REC). Exposure rate readings (window open and window closed) were taken at a distance of 2.5 centimeters (cm) and 30 cm from the surface of each smear. Gross beta-gamma and alpha counts of each smear were also performed. The smear samples were analyzed by gamma energy analysis (GEA). Alpha energy analysis (AEA) and strontium-90 analysis were also performed on selected smears. GEA results for one or more samples reported the presence of manganese-54, cobalt-60, silver-108m antimony-125, cesium-134, cesium-137, europium-154, europium-155, and americium-241. AEA results reported the presence of plutonium-239/240, plutonium-238/ 241 Am, curium-243/244, curium-242, and americium-243. Tables 5 through 9 present a summary by location of the estimated maximum removable and total contamination levels in the Room 147 hoods, the SMF, and the REC. The smear sample survey data and laboratory analytical results are presented in tabular form by sample in Appendix A. The Appendix A tables combine survey data documented in radiological survey reports found in Appendix B and laboratory analytical results reported in the 324 Building Physical and Radiological Characterization Study (Berk, Hill, and Landsman 1998), supplemented by the laboratory analytical results found in Appendix C.

  8. Summary of Research 1997

    OpenAIRE

    Maier, William B.; Cleary, David D.

    1997-01-01

    This report contains summaries of research projects in the Department of Physics. A list of recent publications in also included which consists of conference presentations and publications, books, contributions to books, published jounal papers, technical reports, and thesis abstracts.

  9. Program Baseline Change Control Procedure

    International Nuclear Information System (INIS)

    1993-02-01

    This procedure establishes the responsibilities and process for approving initial issues of and changes to the technical, cost, and schedule baselines, and selected management documents developed by the Office of Civilian Radioactive Waste Management (OCRWM) for the Civilian Radioactive Waste Management System. This procedure implements the OCRWM Baseline Management Plan and DOE Order 4700.1, Chg 1. It streamlines the change control process to enhance integration, accountability, and traceability of Level 0 and Level I decisions through standardized Baseline Change Proposal (BCP) forms to be used by the Level 0, 1, 2, and 3 Baseline Change Control Boards (BCCBs) and to be tracked in the OCRWM-wide Configuration Information System (CIS) Database.This procedure applies to all technical, cost, and schedule baselines controlled by the Energy System Acquisition Advisory Board (ESAAB) BCCB (Level 0) and, OCRWM Program Baseline Control Board (PBCCB) (Level 1). All baseline BCPs initiated by Level 2 or lower BCCBs, which require approval from ESAAB or PBCCB, shall be processed in accordance with this procedure. This procedure also applies to all Program-level management documents controlled by the OCRWM PBCCB

  10. Baseline atmospheric program Australia 1993

    International Nuclear Information System (INIS)

    Francey, R.J.; Dick, A.L.; Derek, N.

    1996-01-01

    This publication reports activities, program summaries and data from the Cape Grim Baseline Air Pollution Station in Tasmania, during the calendar year 1993. These activities represent Australia's main contribution to the Background Air Pollution Monitoring Network (BAPMoN), part of the World Meteorological Organization's Global Atmosphere Watch (GAW). The report includes 5 research reports covering trace gas sampling, ozone and radon interdependence, analysis of atmospheric dimethylsulfide and carbon-disulfide, sampling of trace gas composition of the troposphere, and sulfur aerosol/CCN relationship in marine air. Summaries of program reports for the calendar year 1993 are also included. Tabs., figs., refs

  11. 100-B area technical baseline report

    International Nuclear Information System (INIS)

    Carpenter, R.W.

    1994-01-01

    This document supports the environmental remediation effort of the 100-B Area by providing remediation planners with key data that characterize the 100-B and 100-C Reactor sites. It provides operational histories of the 100-B and 100-C Reactors and each of their associated liquid and solid waste sites

  12. 100-B area technical baseline report

    Energy Technology Data Exchange (ETDEWEB)

    Carpenter, R.W.

    1994-09-01

    This document supports the environmental remediation effort of the 100-B Area by providing remediation planners with key data that characterize the 100-B and 100-C Reactor sites. It provides operational histories of the 100-B and 100-C Reactors and each of their associated liquid and solid waste sites.

  13. Co-ordination of the international network of nuclear structure and decay data evaluators. Summary report of an IAEA technical meeting

    Energy Technology Data Exchange (ETDEWEB)

    Pronyaev, V G; Nichols, A L; Tuli, J [eds.

    2004-03-01

    The IAEA Nuclear Data Section convened the 15th meeting of the Network of Nuclear Structure and Decay Data Evaluators at the IAEA Headquarters, Vienna, 10-14 November 2003. This meeting was attended by 23 scientists from 11 Member States concerned with the compilation, evaluation and dissemination of nuclear structure and decay data. A summary of the meeting, the recommendations, data centre reports and the various proposals considered, modified and agreed by the participants are contained within this document. Nuclear data are essential to the development, implementation and maintenance of all nuclear technologies. The international network of Nuclear Structure and Decay Data (NSDD) Evaluators is sponsored by the IAEA, and consists of evaluation groups and data service centers in several countries. This network has the objective of providing up-to-date nuclear structure and decay data for all known nuclides by evaluating all existing experimental data. Data resulting from this international evaluation collaboration is included in the Evaluated Nuclear Structure Data File (ENSDF) and published in the journals Nuclear Physics A and Nuclear Data Sheets. The results represent the recommended 'best values' for the various nuclear structure and decay data parameters. Recommended values are made available to users by means of various media, such as the world wide web, CD-ROMs, wall charts of the nuclides, handbooks, nuclear wallet cards and others. Participants discussed a wide range of technical matters, and the recommendations of improving the quality of NSDD evaluations. A list of actions was also prepared for implementation during the course of the next two years. NSDD members prepared many recommendations for the IAEA and the major evaluation centers, which are aimed at improving the technical support towards the network and streamlining the organization of work. These consensus conclusions include: the development and exchange of programming products; revision of

  14. Project management training : [technical summary].

    Science.gov (United States)

    2011-01-01

    In 2005, the Indiana Department of Transportation (INDOT) went through a complete reorganization of its operations going from centralized to decentralized (District) management. This reorganization gave Districts autonomy to manage construction proje...

  15. Air void clustering : [technical summary].

    Science.gov (United States)

    2015-06-01

    Air void clustering around coarse aggregate in concrete has been : identified as a potential source of low strengths in concrete mixes by : several Departments of Transportation around the country. Research : was carried out to (1) develop a quantita...

  16. Climate Change 2014: Technical Summary

    Science.gov (United States)

    Field, Chrisopher B.; Barros, Vicente; Mach, Katherine; Mastrandrea, Michael; van Aalst, Maarten; Adger, Niel; Arent, Douglas J; Barnett, Jonathan; Betts, Richard; Bilir, Eren; Birkmann, Joern; Carmin, Joann; Chadee, Dave; Challinor, Andrew; Chaterjee, Monalisa; Cramer, Wolfgang; Davidson, Debra; Estrada, Yuka; Gatusso, Jean-Pierre; Hijioka, Yasuakai; Yohe, Gary; Hiza, Margaret; Hoegh-Guldberg, Ove; Huang, He-Qing; Insarov, Gregory; Jones, Roger; Kovats, Sari; Lankao, Patricia Romero; Larsen, Joan Nymand; Losada, Iñigo; Marengo, José; McLean, Roger; Mearns, Linda; Mechler, Reinhard; Morton, John; Niang, Isabelle; Oki, Taikan; Olwoch, Jane Mukarugwiza; Opondo, Maggie; Poloczanska, Elvira; Pörtner, Hans -O.; Reisinger, Andy; Revi, Aromar; Schmidt, Daniela; Shaw, Rebecca; Solecki, William; Stone, Dáithí; Stone, John; Strzepek, Ken; Suarez, Avelino G.; Tschakert, Petra; Valentini, Riccardo; Vicuna, Sebastian; Villamizar, Alicia; Vincent, Katharine; Warren, Rachel; White, Leslie; Wilbanks, Thomas; Wong, Poh Poh

    2014-01-01

    Human interference with the climate system is occurring (WGI AR5 SPM Section D.3; WGI AR5 Sections 2.2, 6.3, 10.3 to 10.6, 10.9). Climate change poses risks for human and natural systems. The assessment of impacts, adaptation, and vulnerability in the Working Group II contribution to the IPCC’s Fifth Assessment Report (WGII AR5) evaluates how patterns of risks and potential benefits are shifting due to climate change. It considers how impacts and risks related to climate change can be reduced and managed through adaptation and mitigation. The report assesses needs, options, opportunities, constraints, resilience, limits, and other aspects associated with adaptation. It recognizes that risks of climate change will vary across regions and populations, through space and time, dependent on myriad factors including the extent of adaptation and mitigation. For the past 2 decades, IPCC’s Working Group II has developed assessments of climate change impacts, adaptation, and vulnerability. The WGII AR5 builds from the WGII contribution to the IPCC’s Fourth Assessment Report (WGII AR4), published in 2007, and the Special Report on Managing the Risks of Extreme Events and Disasters to Advance Climate Change Adaptation (SREX), published in 2012. It follows the Working Group I contribution to the AR5. The WGII AR5 is presented in two parts (Part A: Global and Sectoral Aspects, and Part B: Regional Aspects), reflecting the expanded literature basis and multidisciplinary approach, increased focus on societal impacts and responses, and continued regionally comprehensive coverage. [1.1 to 1.3] The number of scientific publications available for assessing climate change impacts, adaptation, and vulnerability more than doubled between 2005 and 2010, with especially rapid increases in publications related to adaptation, allowing for a more robust assessment that supports policymaking (high confidence). The diversity of the topics and regions covered has similarly expanded, as has the geographic distribution of authors contributing to the knowledge base for climate change assessments. Authorship of climate change publications from developing countries has increased, although it still represents a small fraction of the total. The unequal distribution of publications presents a challenge to the production of a comprehensive and balanced global assessment.

  17. Assessing deposition of airborne particulates and gases in the Selkirk area using lichens growing on tree trunks : non-technical summary

    International Nuclear Information System (INIS)

    Ehnes, J.

    2002-01-01

    An independent study was conducted to address the public concern regarding airborne emissions from Manitoba Hydro's coal-fired electricity generating station located in the Selkirk area. This document is a non-technical summary of the report issued by Ecostem Ltd. Since there are no air quality monitoring stations in the study area which covers more than 1,000 square km, Ecostem used lichens as biological indicators of historical deposition of airborne dust and gases. The sources of airborne dust and gases include urban centres, agriculture, pesticides, fertilizers, waste burning, vehicle use and manufacturing. Lichens have been commonly used as indicators since 1866. They provide useful information because they are long-lived, are not mobile, acquire most of their nutrients from the atmosphere, retain the airborne deposition they initially trap, and they can accumulate airborne particles year round. It is possible to obtain a record of the chemicals that have been present in the air by simply analyzing the lichen tissue. This study used the concentrations of various chemical elements in lichen tissue and the distribution and abundance of lichen species to see if airborne particulates were substantially elevated in the Selkirk area and if so, to determine if the coal-fired generating station was the apparent source of the pollution. A total of 62 stations and lichens on more than 400 trees were sampled. Sulphur, a fingerprint for gaseous emissions from the generating station, had tissue concentrations that were 1.32 times higher. Statistical analysis suggests that barium, boron and strontium were the clearest fingerprint elements for generating station emissions. Tissue concentrations of antimony, arsenic, cadmium, chromium, copper, iron, lead, manganese, mercury, molybdenum, nickel, selenium, silver, thallium, tin, vanadium and zinc were examined further because they are considered to be toxic. It was noted that a conclusion regarding human health cannot be made

  18. Alternative technical summary report for immobilized disposition in deep boreholes: Immobilized disposal of plutonium in coated ceramic pellets in grout without canisters, Version 4.0. Fissile materials disposition program

    Energy Technology Data Exchange (ETDEWEB)

    Wijesinghe, A.M.

    1996-08-23

    This paper summarizes and compares the immobilized and direct borehole disposition alternatives previously presented in the alternative technical summary. The important design concepts, facility features and operational procedures are first briefly described. This is followed by a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition.

  19. Alternative technical summary report for immobilized disposition in deep boreholes: Immobilized disposal of plutonium in coated ceramic pellets in grout without canisters, Version 4.0. Fissile materials disposition program

    International Nuclear Information System (INIS)

    Wijesinghe, A.M.

    1996-01-01

    This paper summarizes and compares the immobilized and direct borehole disposition alternatives previously presented in the alternative technical summary. The important design concepts, facility features and operational procedures are first briefly described. This is followed by a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition

  20. Conference summaries

    Energy Technology Data Exchange (ETDEWEB)

    Reynolds, Tim [Inta Communication Limited for European Service Network/ DG Research, Trillium House, 32 New Street, St. Neots, Cambridge PE19 1AJ (United Kingdom)

    2004-07-01

    The summaries were derived from presentations, interviews and discussions at the conference. The summaries are given at two levels, overall for the conference and for specific sessions as follows: 1) Overall Conference: 'A Sound Scientific Basis for Serious Decisions; 2) Sessions on EC Policy and Socio-Political Issues: 'Promoting Safety and Protecting Society'; 3) Session on P and T: 'Partitioning and Transmutation: A Technical Fix or Technical Training?'; 4) Sessions on Geological Disposal and Research Networking: 'No Technical Barriers to Geological Disposal'. First an overall summary of Euradwaste '04 is presented. Significant progress was made on the technical and scientific basis for geological disposal of radioactive waste during the European Commission's Fifth EURATOM Framework Programme for Research (FP5). Deep geological disposal is technically feasible now and can demonstrate the guarantees of long-term isolation and protection of the public. In parallel, socio-political studies have produced methodologies for constructive dialogue with potential host communities that reflect the honesty and openness expected by a democratic society. A harmonized legislative framework for nuclear safety and waste disposal across the enlarged European Union is currently being discussed. Disposal in deep (> 300 metre) geological repositories, the favoured strategy in Europe for long-lived high-level radioactive waste, is now possible. The Sessions on EC Policy and Socio-Political Issues are summarized as follows. The opening day of Euradwaste '04 focused on European Commission policy, including the proposed Directives on disposal of radioactive waste and nuclear safety and socio-political aspects including governance and decision making, public perception/acceptance of waste disposal and its sustainability. A decision on the proposed package will now be made after Union enlargement. Public agreement on the siting of

  1. Summary Report of an IAEA Technical Meeting on Co-ordination of the International Network of Nuclear Structure and Decay Data Evaluators

    International Nuclear Information System (INIS)

    Abriola, D.; Dimitriou, P.; Ricard-McCutchan, E.; Tuli, J.K.

    2013-08-01

    Biennial meetings of the International Network of Nuclear Structure and Decay Data (NSDD) evaluators are held under the auspices of the IAEA. The Network consists of evaluation groups and data service centres in several countries. This Network has the objective of providing up-to-date nuclear structure and decay data for all known nuclides by evaluating all existing experimental data. Data resulting from this international evaluation collaboration are included in the Evaluated Nuclear Structure Data File (ENSDF) and published in the journals Nuclear Physics A and Nuclear Data Sheets (NDS). The results represent the recommended 'best values' for the various nuclear structure and decay data properties. These data and bibliographic details are also available through the World Wide Web, CD-ROM, wall charts of the nuclides, Nuclear Wallet Cards and other such media. The US efforts are coordinated by the Coordinating Committee of the US Nuclear Data Program. The ENSDF master database is maintained by the US National Nuclear Data Centre at Brookhaven National Laboratory, and these data are also available from other distribution centres including the IAEA Nuclear Data Section. Biennial meetings of the Network are sponsored by the IAEA Nuclear Data Section, and have the following objectives: (a) coordination of the work of all centres and groups participating in the compilation, evaluation and dissemination of NSDD; (b) maintenance of and improvements to the standards and rules governing NSDD evaluations; (c) review of the development and common use of computerized systems and databases maintained specifically for this activity. In those meetings detailed studies and discussions are undertaken over a five-day period. This document represents a summary of the Network meeting held at the Kuwait Foundation for the Advancement of Sciences (KFAS), Safat, Kuwait, from 27 to 31 January 2013. Thirty-six nuclear data specialists from seventeen countries attended this meeting to

  2. Summary Report of an IAEA Technical Meeting on Co-ordination of the International Network of Nuclear Structure and Decay Data Evaluators

    Energy Technology Data Exchange (ETDEWEB)

    Abriola, D.; Dimitriou, P. [IAEA Nuclear Data Section, Vienna (Austria); Ricard-McCutchan, E.; Tuli, J. K. [Brookhaven National Laboratory, Upton, NY (United States)

    2013-08-15

    Biennial meetings of the International Network of Nuclear Structure and Decay Data (NSDD) evaluators are held under the auspices of the IAEA. The Network consists of evaluation groups and data service centres in several countries. This Network has the objective of providing up-to-date nuclear structure and decay data for all known nuclides by evaluating all existing experimental data. Data resulting from this international evaluation collaboration are included in the Evaluated Nuclear Structure Data File (ENSDF) and published in the journals Nuclear Physics A and Nuclear Data Sheets (NDS). The results represent the recommended 'best values' for the various nuclear structure and decay data properties. These data and bibliographic details are also available through the World Wide Web, CD-ROM, wall charts of the nuclides, Nuclear Wallet Cards and other such media. The US efforts are coordinated by the Coordinating Committee of the US Nuclear Data Program. The ENSDF master database is maintained by the US National Nuclear Data Centre at Brookhaven National Laboratory, and these data are also available from other distribution centres including the IAEA Nuclear Data Section. Biennial meetings of the Network are sponsored by the IAEA Nuclear Data Section, and have the following objectives: (a) coordination of the work of all centres and groups participating in the compilation, evaluation and dissemination of NSDD; (b) maintenance of and improvements to the standards and rules governing NSDD evaluations; (c) review of the development and common use of computerized systems and databases maintained specifically for this activity. In those meetings detailed studies and discussions are undertaken over a five-day period. This document represents a summary of the Network meeting held at the Kuwait Foundation for the Advancement of Sciences (KFAS), Safat, Kuwait, from 27 to 31 January 2013. Thirty-six nuclear data specialists from seventeen countries attended this meeting to

  3. Integrated planning: A baseline development perspective

    International Nuclear Information System (INIS)

    Clauss, L.; Chang, D.

    1994-01-01

    The FEMP Baseline establishes the basis for integrating environmental activity technical requirements with their cost and schedule elements. The result is a path forward to successfully achieving the FERMCO mission. Specific to cost management, the FEMP Baseline has been incorporate into the FERMCO Project Control System (PCS) to provide a time-phased budget plan against which contractor performance is measured with an earned value management system. The result is the Performance Measurement Baseline (PMB), an important tool for keeping cost under control

  4. Technical aspects of atomic and molecular data processing and exchange. 19. meeting of the A+M Data Centres and ALADDIN Network. Summary report of an IAEA technical meeting

    International Nuclear Information System (INIS)

    Humbert, D.

    2008-05-01

    The proceedings of the IAEA Technical Meeting on Technical Aspects of Atomic and Molecular Data Processing and Exchange (19th Meeting of A+M Data Centres and ALADDIN Network), held on 3-5 October, 2007 in Vienna, Austria, are briefly described. Conclusions and recommendations are presented concerning various proposed projects and their priorities involving A+M data compilation and evaluation and technical aspects of data processing, exchange, and distribution. (author)

  5. Summary report of IAEA technical meeting on technical aspects of atomic and molecular data processing and exchange - 18th meeting of the A+M Data Centres and ALADDIN Network

    International Nuclear Information System (INIS)

    Hubert, D.

    2006-01-01

    The IAEA Technical Meeting on 'Technical Aspects of Atomic and Molecular Data Processing and Exchange - 18th Meeting of A+M Data Centres and ALADDIN Network' was held on 10-11 October 2005, in Vienna, Austria. The discussions and presentations focused on the priorities in A+M data compilation and evaluation, and are summarized in this report. Conclusions and recommendations on the technical aspects of data processing, exchange and distribution are also presented. (author)

  6. Executive summary

    International Nuclear Information System (INIS)

    2002-01-01

    On 18 May 2001, the Finnish Parliament ratified the Decision in Principle on the final disposal facility for spent nuclear fuel at Olkiluoto, within the municipality of Eurajoki. The Municipality Council and the government has made positive decisions earlier, at the end of 2000, and in compliance with the Nuclear Energy Act, Parliament's ratification was then required. The decision is valid for the spent fuel generated by the existing Finnish nuclear power plants and means that the construction of the final disposal facility is considered to be in line with the overall good of society. Earlier steps included, amongst others, the approval of the technical project by the Safety Authority. Future steps include construction of an underground rock characterisation facility, ONKALO (2003-2004), and application for separate construction and operating licences for the final disposal facility (from about 2010). How did this political and societal decision come about? The FSC Workshop provided the opportunity to present the history leading up to the Decision in Principle (DiP), and to examine future perspectives with an emphasis on stakeholder involvement. This Executive Summary gives an overview of the presentations and discussions that took place at the workshop. It presents, for the most part, a factual account of the individual presentations and of the discussions that took place. It relies importantly on the notes that were taken at the meeting. Most materials are elaborated upon in a fuller way in the texts that the various speakers and session moderators contributed for these proceedings. The structure of the Executive Summary follows the structure of the workshop itself. Complementary to this Summary and also provided with this document, is a NEA Secretariat's perspective aiming to place the results of all discussions, feedback and site visit into an international perspective. (authors)

  7. Kansas Department of Transportation's enterprise energy and carbon accounting and utility research phase 1B : embodied and operational energy and carbon in buildings and vehicles : technical summary.

    Science.gov (United States)

    2012-03-01

    Many organizations have become concerned about the environmental impact of their facilities and operations. In order to lessen environmental impact, quantitative assessment of practice based on improvements from a baseline condition is needed. The Ka...

  8. Comprehensive Technical Report of the Inquiry into the Application of Living Systems Theory to 41 U. S. Army Battalions: Executive Summary. Volume 1

    Science.gov (United States)

    1984-11-01

    information such as statutory and executive directives, regulations, and technical manuals is blended with matter/energy (people, equipment, and...which might be initiated in order to counteract these potential pathologies. An organizacion , like an organism, cannot survive when its basic processes...Normative Tables and Performance Indicator Scales presented in the study. The Tables and Scales, much like the specification in a technical ,. manual , permit

  9. Executive Summary

    International Nuclear Information System (INIS)

    2014-01-01

    Each session of the workshop consisted of a number of presentations followed by a panel discussion moderated by the session Chairs. A summary of each session and subsequent discussion that ensued are provided. Session 1: National approaches for long term interim storage facilities. Seven papers were presented during this session by representatives of research institutes in USA (EPRI) and in Norway (IFE), governmental authorities for the nuclear industry in Finland (STUK) and Slovak Republic (UJD), technical support organizations in Germany (GRS) and France (IRSN) and the public company in charge of waste management in Spain (ENRESA). The papers discussed the national policy, the regulatory framework and the current situation for storage of SF and HLW in various European countries (Germany, Spain, Finland, Norway and Slovak Republic). The main activities the EPRI is undertaking to establish the technical bases for extended (long-term) storage and the IRSN's definition of the safety principles and objectives for new storage facilities regarding long-term storage are also discussed. Session 2: Safety requirements, regulatory framework and implementation issues. Eleven papers were presented during this session by representatives from international groups (the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency (NEA)), representatives of regulatory bodies from the United States (Nuclear Regulatory Commission) and Germany (Bundesamt fuer Strahlenschutz (BfS)), German Federal Institute for Materials Research and Testing (BAM), operators from the United Kingdom (Sellafield Limited, UK) and France (EDF), vendors (AREVA), and representatives of TSOs in Germany (TUV and Oko-Institut). Session 3: Technical issues and operational experience, needs for R and D. This session was chaired by Karl Wasinger (AREVA, Germany) and Fumihisa Nagase (JAEA, Japan). Ten papers were presented during this session by representatives of research institutes of Japan (CRIEPI

  10. Technical aspects of atomic and molecular data processing and exchange, 20. meeting of the A+M Data Centres and ALADDIN Network. Summary report of an IAEA technical meeting

    International Nuclear Information System (INIS)

    Humbert, D.; Braams, B.J.

    2010-01-01

    The proceedings of the IAEA Advisory Group Meeting on Technical Aspects of Atomic and Molecular Data Processing and Exchange (20th Meeting of A+M Data Centres Network), 7-9 September 2009 at IAEA Headquarters in Vienna, are summarized. The meeting conclusions and recommendations on priorities in A+M data compilation and evaluation and on technical aspects of data processing and exchange are also presented. (author)

  11. The second iteration of the Systems Prioritization Method: A systems prioritization and decision-aiding tool for the Waste Isolation Pilot Plant: Volume 2, Summary of technical input and model implementation

    Energy Technology Data Exchange (ETDEWEB)

    Prindle, N.H.; Mendenhall, F.T.; Trauth, K.; Boak, D.M. [Sandia National Labs., Albuquerque, NM (United States); Beyeler, W. [Science Applications International Corp., Albuquerque, NM (United States); Hora, S. [Hawaii Univ., Hilo, HI (United States); Rudeen, D. [New Mexico Engineering Research Inst., Albuquerque, NM (United States)

    1996-05-01

    The Systems Prioritization Method (SPM) is a decision-aiding tool developed by Sandia National Laboratories (SNL). SPM provides an analytical basis for supporting programmatic decisions for the Waste Isolation Pilot Plant (WIPP) to meet selected portions of the applicable US EPA long-term performance regulations. The first iteration of SPM (SPM-1), the prototype for SPM< was completed in 1994. It served as a benchmark and a test bed for developing the tools needed for the second iteration of SPM (SPM-2). SPM-2, completed in 1995, is intended for programmatic decision making. This is Volume II of the three-volume final report of the second iteration of the SPM. It describes the technical input and model implementation for SPM-2, and presents the SPM-2 technical baseline and the activities, activity outcomes, outcome probabilities, and the input parameters for SPM-2 analysis.

  12. The second iteration of the Systems Prioritization Method: A systems prioritization and decision-aiding tool for the Waste Isolation Pilot Plant: Volume 2, Summary of technical input and model implementation

    International Nuclear Information System (INIS)

    Prindle, N.H.; Mendenhall, F.T.; Trauth, K.; Boak, D.M.; Beyeler, W.; Hora, S.; Rudeen, D.

    1996-05-01

    The Systems Prioritization Method (SPM) is a decision-aiding tool developed by Sandia National Laboratories (SNL). SPM provides an analytical basis for supporting programmatic decisions for the Waste Isolation Pilot Plant (WIPP) to meet selected portions of the applicable US EPA long-term performance regulations. The first iteration of SPM (SPM-1), the prototype for SPM< was completed in 1994. It served as a benchmark and a test bed for developing the tools needed for the second iteration of SPM (SPM-2). SPM-2, completed in 1995, is intended for programmatic decision making. This is Volume II of the three-volume final report of the second iteration of the SPM. It describes the technical input and model implementation for SPM-2, and presents the SPM-2 technical baseline and the activities, activity outcomes, outcome probabilities, and the input parameters for SPM-2 analysis

  13. Mergeable summaries

    DEFF Research Database (Denmark)

    Agarwal, Pankaj K.; Graham, Graham; Huang, Zengfeng

    2013-01-01

    We study the mergeability of data summaries. Informally speaking, mergeability requires that, given two summaries on two datasets, there is a way to merge the two summaries into a single summary on the two datasets combined together, while preserving the error and size guarantees. This property m...

  14. Co-ordination of the International Network of Nuclear Structure and Decay Data Evaluators. Summary report of an IAEA Technical Meeting

    International Nuclear Information System (INIS)

    Nichols, A.L.; Tuli, J.K.

    2007-09-01

    The IAEA Nuclear Data Section convened the 17th meeting of the International Network of Nuclear Structure and Decay Data Evaluators in St. Petersburg, Russian Federation, 11-15 June 2007. This meeting was attended by 27 scientists from 13 Member States concerned with the compilation, evaluation and dissemination of nuclear structure and decay data. A summary of the meeting, recommendations/conclusions, data centre reports, and various proposals considered, modified and agreed by the participants are contained within this document. (author)

  15. Healthcare. Executive Summary

    Science.gov (United States)

    Carnevale, Anthony P.; Smith, Nicole; Gulish, Artem; Beach, Bennett H.

    2012-01-01

    This executive summary highlights several findings about healthcare. These are: (1) Healthcare is 18 percent of the U.S. economy, twice as high as in other countries; (2) There are two labor markets in healthcare: high-skill, high-wage professional and technical jobs and low-skill, low-wage support jobs; (3) Demand for postsecondary education in…

  16. Aligning Career and Technical Education with High-Wage and High-Demand Occupations in Tennessee. Summary. Issues & Answers. REL 2011-No. 111

    Science.gov (United States)

    Mokher, Christine

    2011-01-01

    This study examines the availability of career and technical education program areas in Tennessee high schools, concentrations (a three-or-more credit sequence in a program area) completed by 2007/08 high school graduates, and how these concentrations align with jobs in the labor market. It looks at how these outcomes differ, statewide and by…

  17. Researching College- and Career Ready Standards to Improve Student Outcomes: Technical Working Group Meeting. Meeting Summary (Washington, DC, August 19-20, 2013)

    Science.gov (United States)

    Institute of Education Sciences, 2013

    2013-01-01

    In August, IES worked with the National Science Foundation and the Eunice Kennedy Shriver National Institute of Child Health and Human Development to convene a technical working group to discuss research objectives related to college- and career-ready standards in English language arts and mathematics. Forty people (including researchers,…

  18. Co-ordination of the International Network of Nuclear Structure and Decay Data Evaluators. Summary report of an IAEA technical meeting

    International Nuclear Information System (INIS)

    Abriola, D.; Tuli, J.K.

    2009-10-01

    The IAEA Nuclear Data Section convened the 18th meeting of the International Network of Nuclear Structure and Decay Data Evaluators at the IAEA Headquarters, Vienna, 23 to 27 March 2009. This meeting was attended by 22 scientists from 14 Member States, plus IAEA staff, concerned with the compilation, evaluation and dissemination of nuclear structure and decay data. A summary of the meeting, recommendations/conclusions, data centre reports, and various proposals considered, modified and agreed by the participants are contained within this document. (author)

  19. Summary Report of an IAEA Technical Meeting on Co-ordination of the International Network of Nuclear Structure and Decay Data Evaluators

    Energy Technology Data Exchange (ETDEWEB)

    Abriola, D [IAEA Nuclear Data Section, Vienna (Austria); Nichols, A L [Departments of Physics, University of Surrey, Guildford (United Kingdom); Tuli, J K [Brookhaven National Laboratory, Brookhaven, Upton, NY (United States)

    2011-10-15

    The 19th meeting of the International Network of Nuclear Structure and Decay Data Evaluators was convened at the IAEA Headquarters, Vienna, from 4 to 8 April 2011, by the staff members of IAEA, Nuclear Data Section. This meeting was attended by 35 scientists from 20 Member States, plus IAEA staff, concerned with the compilation, evaluation and dissemination of nuclear structure and decay data. A summary of the meeting, data centre reports, various proposals considered, modified and agreed by the participants, and recommendations/conclusions are presented within this document. (author)

  20. Summary Report of an IAEA Technical Meeting on Co-ordination of the International Network of Nuclear Structure and Decay Data Evaluators

    International Nuclear Information System (INIS)

    Abriola, D.; Nichols, A.L.; Tuli, J.K.

    2011-10-01

    The 19th meeting of the International Network of Nuclear Structure and Decay Data Evaluators was convened at the IAEA Headquarters, Vienna, from 4 to 8 April 2011, by the staff members of IAEA, Nuclear Data Section. This meeting was attended by 35 scientists from 20 Member States, plus IAEA staff, concerned with the compilation, evaluation and dissemination of nuclear structure and decay data. A summary of the meeting, data centre reports, various proposals considered, modified and agreed by the participants, and recommendations/conclusions are presented within this document. (author)

  1. Co-ordination of the International Network of Nuclear Structure and Decay Data Evaluators. Summary report of an IAEA technical meeting

    Energy Technology Data Exchange (ETDEWEB)

    Nichols, A L; Tuli, J K [International Atomic Energy Agency, Nuclear Data Section, Vienna (Austria)

    2005-09-15

    The IAEA Nuclear Data Section convened the 16th meeting of the International Network of Nuclear Structure and Decay Data Evaluators at the Department of Physics and Astronomy, McMaster University, Hamilton, Canada, 6-10 June 2005. This meeting was attended by 33 scientists from 12 Member States concerned with the compilation, evaluation and dissemination of nuclear structure and decay data. A summary of the meeting, recommendations/conclusions, data centre reports, and various proposals considered, modified and agreed by the participants are contained within this document. (author)

  2. Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Introductory part and summaries

    International Nuclear Information System (INIS)

    1999-11-01

    Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan and comprises seven chapters. Chapter I briefly describes the importance of HLW management in promoting nuclear energy utilization. According to the long-term program, the HLW separated from spent fuels at reprocessing plants is to be vitrified and stored for a period of 30 to 50 years to allow cooling, then be disposed of in a deep geological formation. Chapter II mainly explains the concepts of geological disposal in Japan. Chapters III to V are devoted to discussions on three important technical elements (the geological environment of Japan, engineering technology and safety assessment of the geological disposal system) which are necessary for reliable realization of the geological disposal concept. Chapter VI demonstrates the technical ground for site selection and for setup of safety standards of the disposal. Chapter VII summarizes together with plans for future research and development. (Ohno, S.)

  3. Management summary

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    A most pressing problem in many environmental assessments is determining the extent of contamination to the biosphere resulting from a given activity. This could result from the planned or accidental release of a contaminant to the environment and its subsequent transport through air, water, or the food chain. In either case, three critical questions need to be raised in the environmental assessment of the problem: Where are the contaminants; When will they arrive at a specific location; How much of the contaminant will be at the point of uptake. The location of the contaminant is important, since a contaminant isolated from man both now and in the future may represent little hazard, even in rather large quantities. Under other conditions, small amounts of contaminants arriving at critical locations over a short period may involve severe hazard. The problem of location is simplified by concentrating on those places where the contaminants will interface with the biosphere. Applications in evaluating the consequences of ground water contamination are discussed. Environmental consequences or impacts are most effectively and efficiently communicated by: Blending extensive technical results and reducing them to simple summary relationships, i.e., the arrival distributions; focusing on the arrival distributions as the central theme of communication efforts; and determining quantitative consequences or impacts to the biosphere through use of the arrival distributions. Appropriately applied, these principles can reduce a voluminous impact statement on subsurface pollution to a few pages that are directly useful to decision-makers and the public

  4. Executive Summary

    International Nuclear Information System (INIS)

    2013-01-01

    countries (MC) and concerned both initial safety assessment of new facilities and reassessment of existing ones (periodic safety review). It also considered trends of future improvement of safety assessment techniques. The workshop was organised in an opening session, four technical sessions, one special session and a conclusion session. The technical sessions were focussed on: - General approach including human aspects (9 papers); - Front end facilities (5 papers); - Chemical hazards - release limits (6 papers); and - Back end facilities (6 papers). In addition, a special session (4 presentations) was held to discuss the lessons learnt for FCFs from the Fukushima accident in Japan. The workshop ended with an organized site visit to Cameco Corporation's Port Hope Conversion Facility in Port Hope, Ontario on the last day of the workshop. This paper presents the Summary of the technical and special sessions, the General Conclusions and Recommendation of the workshop and some future directions

  5. Scientific and technical conference. Problems and horizons of development of chemical and radiochemical control in nuclear energetics. Collection of summaries of reports

    International Nuclear Information System (INIS)

    2001-01-01

    During scientific and technical conference on problems of development of chemical and radiochemical control in nuclear energetics following themes were considered: the problems of methodological and instrumental assurance of chemical and radiochemical control at working nuclear power plants and nuclear energetic units; modern conceptions of automation systems construction of chemical and radiochemical control on the basis of intellectual measuring channels; the ways of decision of generally system problems of organization and management of chemical and radiochemical control using computed technologies; the problems of certification of chemical and radiochemical methods of measuring in nuclear energetics [ru

  6. SAM Technical Review Committee Final Report: Summary and Key Recommendations from the Onsite TRC Meeting Held April 22-23, 2013

    Energy Technology Data Exchange (ETDEWEB)

    Blair, N.; Dobos, S.; Janzou, S.; Gilman, P.; Freeman, J.; Kaffine, L.

    2013-08-01

    The System Advisor Model (SAM) is a broad and robust set of models and frameworks for analyzing both system performance and system financing. It does this across a range of technologies dominated by solar technologies including photovoltaics (PV) and concentrated solar power (CSP). The U.S. Department of Energy (DOE) Solar Energy Technology Program requested the SAM development team to review the photovoltaic performance modeling with the development community and specifically, with the independent engineering community. The report summarizes the major effort for this technical review committee (TRC).

  7. Spent-Fuel Test - Climax: An evaluation of the technical feasibility of geologic storage of spent nuclear fuel in granite: Executive summary of final results

    International Nuclear Information System (INIS)

    Patrick, W.C.

    1986-01-01

    This summary volume outlines results that are covered in more detail in the final report of the Spent-Fuel Test - Climate project. The project was conducted between 1978 and 1983 in the granitic Climax stock at the Nevada Test Site. Results indicate that spent fuel can be safely stored for periods of years in this host medium and that nuclear waste so emplaced can be safely retrieved. We also evaluated the effects of heat and radiation (alone and in combination) on emplacement canisters and the surrounding rock mass. Storage of the spent-fuel affected the surrounding rock mass in measurable ways, but did not threaten the stability or safety of the facility at any time

  8. Summary of the technical review of the safety analysis reports for packaging (SARP) for the transnuclear transport/storage casks: TN-BRP and TN-REG

    International Nuclear Information System (INIS)

    1986-07-01

    The Safety Analysis Reports for Packaging for two spent fuel shipping casks were technically reviewed by the Oak Ridge National Laboratory. The casks were designed by Transnuclear, Inc., for shipment of 85 Big Rock Point boiling water reactor fuel elements and 40 R.E. Ginna pressurized water reactor fuel elements from West Valley, New York, to Idaho Falls, Idaho. The intent of the review was to ensure compliance of the casks with the requirements the applicable Federal Regulations contained in 10 CFR Pt. 71 and allow issuance of Department of Energy Certificates of Compliance for transport by the Department of Energy Idaho Operations Office. The review was performed by a team of Oak Ridge National Laboratory staff assembled for their expertise in criticality analysis, shielding, metallurgy, nondestructive testing, thermal analysis, structural analysis, and containment. This report describes the review processes, the findings in each technical area, and the overall conclusion that a Certificate of Compliance could be issued for the proposed single shipment under the specified conditions and constraints

  9. Spent nuclear fuel project technical databook

    International Nuclear Information System (INIS)

    Reilly, M.A.

    1998-01-01

    The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values

  10. Spent nuclear fuel project technical databook

    Energy Technology Data Exchange (ETDEWEB)

    Reilly, M.A.

    1998-07-22

    The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values.

  11. Data Evaluation for Atomic, Molecular and Plasma Material Interaction Processes in Fusion. Summary Report of a Joint IAEA-NFRI Technical Meeting

    International Nuclear Information System (INIS)

    Chung, Hyun-Kyung

    2012-12-01

    This report summarizes the proceedings of the Joint IAEA-NFRI Technical Meeting on 'Data Evaluation for Atomic, Molecular and Plasma Material Interaction Processes in Fusion' on 4-7 September 2012. Twenty five participants from 10 Member States and two from the IAEA attended the four-day meeting held at the Daejeon Convention Center in Daejeon, Republic of Korea hosted by the National Fusion Research Institute (NFRI) in conjunction with the 8th International Symposium on Standard Reference Data. The report includes discussions on the issues of the critical assessment of fundamental data required for fusion and plasma applications, meeting conclusions and recommendations. The abstracts of presentations presented in the meeting are attached in the Appendix. (author)

  12. Co-ordination of the International Network of Nuclear Structure and Decay Data Evaluators; Summary Report of an IAEA Technical Meeting

    Energy Technology Data Exchange (ETDEWEB)

    Abriola, D.; Tuli, J.

    2009-03-23

    The IAEA Nuclear Data Section convened the 18th meeting of the International Network of Nuclear Structure and Decay Data Evaluators at the IAEA Headquarters, Vienna, 23 to 27 March 2009. This meeting was attended by 22 scientists from 14 Member States, plus IAEA staff, concerned with the compilation, evaluation and dissemination of nuclear structure and decay data. A summary of the meeting, recommendations/conclusions, data centre reports, and various proposals considered, modified and agreed by the participants are contained within this document. The International Network of Nuclear Structure and Decay Data (NSDD) Evaluators holds biennial meetings under the auspices of the IAEA, and consists of evaluation groups and data service centres in several countries. This network has the objective of providing up-to-date nuclear structure and decay data for all known nuclides by evaluating all existing experimental data. Data resulting from this international evaluation collaboration is included in the Evaluated Nuclear Structure Data File (ENSDF) and published in the journals Nuclear Physics A and Nuclear Data Sheets (NDS).

  13. Program reference schedule baseline

    International Nuclear Information System (INIS)

    1986-07-01

    This Program Reference Schedule Baseline (PRSB) provides the baseline Program-level milestones and associated schedules for the Civilian Radioactive Waste Management Program. It integrates all Program-level schedule-related activities. This schedule baseline will be used by the Director, Office of Civilian Radioactive Waste Management (OCRWM), and his staff to monitor compliance with Program objectives. Chapter 1 includes brief discussions concerning the relationship of the PRSB to the Program Reference Cost Baseline (PRCB), the Mission Plan, the Project Decision Schedule, the Total System Life Cycle Cost report, the Program Management Information System report, the Program Milestone Review, annual budget preparation, and system element plans. Chapter 2 includes the identification of all Level 0, or Program-level, milestones, while Chapter 3 presents and discusses the critical path schedules that correspond to those Level 0 milestones

  14. Long Baseline Observatory (LBO)

    Data.gov (United States)

    Federal Laboratory Consortium — The Long Baseline Observatory (LBO) comprises ten radio telescopes spanning 5,351 miles. It's the world's largest, sharpest, dedicated telescope array. With an eye...

  15. Executive summary

    International Nuclear Information System (INIS)

    2010-01-01

    The special session on Fuel cycle strategies and transition scenarios comprised three invited papers and five oral presentations: INL (USA) was invited to present US activities on fuel cycle transition scenarios; JAEA (Japan) presented the current status of the Japanese nuclear fuel cycle; CEA and EDF (France) gave a presentation on the French fuel cycle strategy and transition scenarios; CEA and INL presented the latest outcomes from the NEA activity on fuel cycle transition scenarios and the European approach; JAEA reported on the results of global scenarios for fast reactor deployment; AECL (Canada) discussed actinide transmutation in Candu reactors, which may efficiently transmute TRU; Materials assessments, which could be used in advanced nuclear fuel cycles from a safeguard perspective, were presented by LANL (USA); The technical session about Impact on P and T on waste management and geological disposal comprised one invited paper and two oral presentations: JAEA presented on the concept of waste management and geological disposal incorporating P and T technology; CIEMAT (Spain) gave a summary of the RED-IMPACT study, which is the study of the impact of P and T on the HLW management programme of the EC; Chalmers University(Sweden) presented an estimation of maximum permissible step losses in P and T processing; The technical session about Progress in transmutation fuels and targets comprised one invited paper and seven oral presentations: The invited talk of the session was given by ITU (EC), on advanced fuel fabrication processes for transmutation; INL presented the development status of transuranic-bearing metal fuels in the USA; CEA summarised European projects on design, development and qualification of advanced fuels for an industrial ADS prototype; The Japanese study of the microstructural evolution and Am migration behaviour in Am-containing MOX fuels at the initial stage of irradiation was presented by JAEA discussed Japanese status on the

  16. FY 1996 activity summary

    International Nuclear Information System (INIS)

    1997-01-01

    The US Department of Energy Office of Nuclear and Facility Safety provides nuclear safety policy, independent technical evaluation, and technical support. A summary of these activities is provided in this report. These include: (1) changing the mission of the former production facilities to storage and waste management; (2) stabilizing nuclear materials not recycled due to production cessation or interruptions; (3) reformulating the authorization basis for existing facilities to convert to a standards based approach for operations consistent with modern expectations; and (4) implementing a modern regulatory framework for nuclear facilities. Enforcement of the Price-Anderson Amendments Act is also reported

  17. Characterization of open-cycle coal-fired MHD generators. Quarterly technical summary report No. 6, October 1--December 31, 1977. [PACKAGE code

    Energy Technology Data Exchange (ETDEWEB)

    Kolb, C.E.; Yousefian, V.; Wormhoudt, J.; Haimes, R.; Martinez-Sanchez, M.; Kerrebrock, J.L.

    1978-01-30

    Research has included theoretical modeling of important plasma chemical effects such as: conductivity reductions due to condensed slag/electron interactions; conductivity and generator efficiency reductions due to the formation of slag-related negative ion species; and the loss of alkali seed due to chemical combination with condensed slag. A summary of the major conclusions in each of these areas is presented. A major output of the modeling effort has been the development of an MHD plasma chemistry core flow model. This model has been formulated into a computer program designated the PACKAGE code (Plasma Analysis, Chemical Kinetics, And Generator Efficiency). The PACKAGE code is designed to calculate the effect of coal rank, ash percentage, ash composition, air preheat temperatures, equivalence ratio, and various generator channel parameters on the overall efficiency of open-cycle, coal-fired MHD generators. A complete description of the PACKAGE code and a preliminary version of the PACKAGE user's manual are included. A laboratory measurements program involving direct, mass spectrometric sampling of the positive and negative ions formed in a one atmosphere coal combustion plasma was also completed during the contract's initial phase. The relative ion concentrations formed in a plasma due to the methane augmented combustion of pulverized Montana Rosebud coal with potassium carbonate seed and preheated air are summarized. Positive ions measured include K/sup +/, KO/sup +/, Na/sup +/, Rb/sup +/, Cs/sup +/, and CsO/sup +/, while negative ions identified include PO/sub 3//sup -/, PO/sub 2//sup -/, BO/sub 2//sup -/, OH/sup -/, SH/sup -/, and probably HCrO/sub 3/, HMoO/sub 4//sup -/, and HWO/sub 3//sup -/. Comparison of the measurements with PACKAGE code predictions are presented. Preliminary design considerations for a mass spectrometric sampling probe capable of characterizing coal combustion plasmas from full scale combustors and flow trains are presented

  18. 原料气压缩机组检修技术总结%Technical summary of maintenance of air compressor unit

    Institute of Scientific and Technical Information of China (English)

    罗伟雄; 符和穗

    2015-01-01

    the raw material pressure reducing unit is the synthetic equipment of 800000 t chemical fertilizer plant in Hainan base of CNOOC chemical Limited by Share Ltd.Since the commissioning of the equipment maintenance tasks have been outside the Commission other chemical inspection unit is responsible for the overhaul of the equipment in 2015 the first time by the company to bear,I encountered in the process of maintenance problems and treatment measures to express, for maintenance or technical personnel to provide reference.%原料气压缩机组为中海油化学股份有限公司海南基地80万 t 化肥装置合成设备。自投产以来该设备的维修任务一直都外委其他化工检修单位负责,2015年该设备的大修首次由本公司独自承担,本人就检修过程中遇到的问题及处理措施进行表述,为检修或技术人员提供参考。

  19. 19th Meeting of the IFRC Subcommittee on Atomic and Molecular Data for Fusion. Summary Report of an IAEA Technical Meeting

    International Nuclear Information System (INIS)

    Braams, Bastiaan J.

    2014-07-01

    The International Fusion Research Council (IFRC) Subcommittee on Atomic and Molecular Data met at IAEA Headquarters in Vienna on 28-29 April 2014 to review the work of the Atomic and Molecular Data Unit (AMDU) within the Nuclear Data Section. The subcommittee heard presentations on the Unit’s activities in the years 2012 and 2013 and discussed priorities for database development and evaluation, coordinated research projects and other meetings, and presentation on the web and elsewhere of the work of the Unit. The IFRC Subcommittee offers the following specific recommendations. • For Coordinated Research Projects in the area of plasma-material interaction highest priority goes to a CRP on erosion and tritium retention for steel surfaces, with emphasis on the kinds of low- or reduced-activation steels that may be used in a reactor. • In the area of atomic and molecular data it is recommended to initiate a new CRP on data for charge exchange processes related to neutral beams. The main topic of interest will be beam interaction with core plasma, but processes relevant to generation of the beam may also be included. • Data for plasma interaction with liquid metals gallium and tin, certain salts and possibly also aluminium, are needed in order to assess uses of these materials in a reactor environment. For a CRP this topic has lower priority than one on steel surfaces, but it is recommended as a good topic for a Technical Meeting. • The Unit should organize again, in 2014 or early 2015, a large “decennial” meeting on atomic, molecular and plasma-material interaction data for fusion science and technology to bring together fusion scientists users of A+M+PMI data and atomic, molecular and materials scientists data producers. • The Unit has the mission to provide internationally recommended and evaluated data for atomic, molecular and plasma-material interaction process and related materials structure properties for fusion science and technology; this is

  20. Neo-adjuvant chemo-radiation of rectal cancer with Volumetric Modulated Arc Therapy: summary of technical and dosimetric features and early clinical experience

    International Nuclear Information System (INIS)

    Richetti, Antonella; Fogliata, Antonella; Clivio, Alessandro; Nicolini, Giorgia; Pesce, Gianfranco; Salati, Emanuela; Vanetti, Eugenio; Cozzi, Luca

    2010-01-01

    To report about initial technical and clinical experience in preoperative radiation treatment of rectal cancer with volumetric modulated arcs with the RapidArc ® (RA) technology. Twenty-five consecutive patients (pts) were treated with RA. All showed locally advanced rectal adenocarcinoma with stage T2-T4, N0-1. Dose prescription was 44 Gy in 22 fractions (or 45 Gy in 25 fractions). Delivery was performed with single arc with a 6 MV photon beam. Twenty patients were treated preoperatively, five did not receive surgery. Twenty-three patients received concomitant chemotherapy with oral capecitabine. A comparison with a cohort of twenty patients with similar characteristics treated with conformal therapy (3DC) is presented as well. From a dosimetric point of view, RA improved conformality of doses (CI 95% = 1.1 vs. 1.4 for RA and 3DC), presented similar target coverage with lower maximum doses, significant sparing of femurs and significant reduction of integral and mean dose to healthy tissue. From the clinical point of view, surgical reports resulted in a down-staging in 41% of cases. Acute toxicity was limited to Grade 1-2 diarrhoea in 40% and Grade 3 in 8% of RA pts, 45% and 5% of 3DC pts, compatible with known effects of concomitant chemotherapy. RA treatments were performed with an average of 2.0 vs. 3.4 min of 3DC. RA proved to be a safe, qualitatively advantageous treatment modality for rectal cancer, showing some improved results in dosimetric aspects

  1. Neo-adjuvant chemo-radiation of rectal cancer with Volumetric Modulated Arc Therapy: summary of technical and dosimetric features and early clinical experience

    Directory of Open Access Journals (Sweden)

    Salati Emanuela

    2010-02-01

    Full Text Available Abstract Background To report about initial technical and clinical experience in preoperative radiation treatment of rectal cancer with volumetric modulated arcs with the RapidArc® (RA technology. Methods Twenty-five consecutive patients (pts were treated with RA. All showed locally advanced rectal adenocarcinoma with stage T2-T4, N0-1. Dose prescription was 44 Gy in 22 fractions (or 45 Gy in 25 fractions. Delivery was performed with single arc with a 6 MV photon beam. Twenty patients were treated preoperatively, five did not receive surgery. Twenty-three patients received concomitant chemotherapy with oral capecitabine. A comparison with a cohort of twenty patients with similar characteristics treated with conformal therapy (3DC is presented as well. Results From a dosimetric point of view, RA improved conformality of doses (CI95% = 1.1 vs. 1.4 for RA and 3DC, presented similar target coverage with lower maximum doses, significant sparing of femurs and significant reduction of integral and mean dose to healthy tissue. From the clinical point of view, surgical reports resulted in a down-staging in 41% of cases. Acute toxicity was limited to Grade 1-2 diarrhoea in 40% and Grade 3 in 8% of RA pts, 45% and 5% of 3DC pts, compatible with known effects of concomitant chemotherapy. RA treatments were performed with an average of 2.0 vs. 3.4 min of 3DC. Conclusion RA proved to be a safe, qualitatively advantageous treatment modality for rectal cancer, showing some improved results in dosimetric aspects.

  2. Summary Report of the Technical Meeting on Inelastic Scattering and Capture Cross-section Data of Major Actinides in the Fast Neutron Region

    International Nuclear Information System (INIS)

    Plompen, Arjan; Kawano, Toshihiko; Capote Noy, Roberto

    2012-05-01

    Recently, tight target uncertainties on the capture and inelastic scattering data for major actinides were derived from advanced reactor sensitivity studies. A Technical Meeting on 'Inelastic Scattering and Capture Cross-section Data of Major Actinides in the Fast Neutron Region' was held at IAEA Headquarters, Vienna, Austria to review the status of nuclear data libraries for these cross sections, the status of the experimental results by which these can be tested and to evaluate what advances in nuclear modeling and measurement technique may bring to improve the knowledge of these cross sections. The participants compared recent evaluations with various modeling approaches that have not yet been adopted in data libraries. Several points of interest were found. First, different evaluations may show very similar performance for macroscopic benchmarks. Second, recent modeling improvements from different communities and using different codes tend to converge on the principles in the case of coupled channel calculations. In particular, it was shown that meaningful results require convergence with respect to the number of coupled channels and the use of the dispersive coupled channels potential based with an isospin dependent term to treat neutrons and protons in a coherent manner appears to be uncontested. Also, the issue regarding the use of transmission coefficients from coupled channels calculations in the Hauser Feshbach model was tackled. Recent and ongoing experimental efforts were presented for capture and inelastic scattering on the major actinides. Results from these are likely to become available in a period from 2 to 5 years. A discussion on the representation of the data in EXFOR revealed that care must be taken interpreting the numbers given in the case of inelastic scattering. It has been a long time since capture data were obtained for fissile nuclei and it is exciting to find new efforts are being considered at LANL, CERN and CENBG/IRMM. It was finally

  3. Research Summaries

    Science.gov (United States)

    Brock, Stephen E., Ed.

    2011-01-01

    This article presents summaries of three articles relevant to school crisis response: (1) "Factors Contributing to Posttraumatic Growth," summarized by Steve DeBlois; (2) "Psychological Debriefing in Cross-Cultural Contexts" (Stacey Rice); and (3) "Brain Abnormalities in PTSD" (Sunny Windingstad). The first summary reports the findings of a…

  4. Concrete Cleaning, Inc. centrifugal shot blaster: Baseline report; Summary

    International Nuclear Information System (INIS)

    1997-01-01

    The centrifugal shot blaster is an electronically operated shot-blast machine that removes layer of concrete of varying depths. Hardened steel shot propelled at a high rate of speed abrades the surface of the concrete. The depth of material removed is determined by the rate of speed the machine is traveling and the volume of shot being fired into the blast chamber. The steel shot is reused until it is pulverized to dust, which is deposited in the waste container with the concrete being removed. Debris is continually vacuumed by a large dust collection system attached to the shot blaster. The safety and health evaluation during the human factors assessment focused on two main areas: noise and dust

  5. Freight Transportation Energy Use : Volume 1. Summary and Baseline Results.

    Science.gov (United States)

    1978-07-01

    The overall design of the TSC Freight Energy Model is presented. A hierarchical modeling strategy is used, in which detailed modal simulators estimate the performance characteristics of transportation network elements, and the estimates are input to ...

  6. First Grade Baseline Evaluation

    Science.gov (United States)

    Center for Innovation in Assessment (NJ1), 2013

    2013-01-01

    The First Grade Baseline Evaluation is an optional tool that can be used at the beginning of the school year to help teachers get to know the reading and language skills of each student. The evaluation is composed of seven screenings. Teachers may use the entire evaluation or choose to use those individual screenings that they find most beneficial…

  7. 75 FR 74026 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2010-11-30

    ... DEPARTMENT OF ENERGY Biomass Research and Development Technical Advisory Committee AGENCY.... SUMMARY: This notice announces an open meeting of the Biomass Research and Development Technical Advisory... participation. This notice announces the meeting of the Biomass Research and Development Technical Advisory...

  8. Rationing with baselines

    DEFF Research Database (Denmark)

    Hougaard, Jens Leth; Moreno-Ternero, Juan D.; Østerdal, Lars Peter Raahave

    2013-01-01

    We introduce a new operator for general rationing problems in which, besides conflicting claims, individual baselines play an important role in the rationing process. The operator builds onto ideas of composition, which are not only frequent in rationing, but also in related problems...... such as bargaining, choice, and queuing. We characterize the operator and show how it preserves some standard axioms in the literature on rationing. We also relate it to recent contributions in such literature....

  9. The TDAQ Baseline Architecture

    CERN Multimedia

    Wickens, F J

    The Trigger-DAQ community is currently busy preparing material for the DAQ, HLT and DCS TDR. Over the last few weeks a very important step has been a series of meetings to complete agreement on the baseline architecture. An overview of the architecture indicating some of the main parameters is shown in figure 1. As reported at the ATLAS Plenary during the February ATLAS week, the main area where the baseline had not yet been agreed was around the Read-Out System (ROS) and details in the DataFlow. The agreed architecture has: Read-Out Links (ROLs) from the RODs using S-Link; Read-Out Buffers (ROB) sited near the RODs, mounted in a chassis - today assumed to be a PC, using PCI bus at least for configuration, control and monitoring. The baseline assumes data aggregation, in the ROB and/or at the output (which could either be over a bus or in the network). Optimization of the data aggregation will be made in the coming months, but the current model has each ROB card receiving input from 4 ROLs, and 3 such c...

  10. Meteorological Summaries

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Multi-year summaries of one or more meteorological elements at a station or in a state. Primarily includes Form 1078, a United States Weather Bureau form designed...

  11. Survey Summary

    Data.gov (United States)

    U.S. Department of Health & Human Services — Nursing home summary information for the Health and Fire Safety Inspections currently listed on Nursing Home Compare, including dates of the three most recent...

  12. OCRWM baseline management procedure for document identifiers

    International Nuclear Information System (INIS)

    1993-03-01

    This procedure establishes a uniform numbering system (document identifier) for all Program and project technical, cost, and schedule baselines, and selected management and procurement documents developed for and controlled by the Office of Civilian Radioactive Waste Management (OCRWM) for the Civilian Radioactive Waste Management System (CRWMS). The document identifier defined in this procedure is structured to ensure that the relational integrity between configuration items (CIs) and their associated documentation and software is maintained, traceable, categorical, and retrievable for the life of the program

  13. TECHNICAL COORDINATION

    CERN Multimedia

    Austin Ball

    Summary of progress since last CMS week. Ten years of construction work have been completed. CMS is closed, in very close to the ideal low luminosity configuration, and performed well in the first tests with LHC beam. Behind this encouraging news is the story of a summer of intense commitment by many teams (from the collaboration and 3 CERN departments) working together, against the clock and despite many minor setbacks, to ensure that the experiment was ready to play a leading role in the excitement of September 10. Following beampipe bakeout and refill with pure neon, a magnificent effort by the ECAL group and the pt 5 technical crew made it possible to install and commission all 4 ECAL endcap Dees before the end of August. In the shadow of this activity, the barrel and forward pixel trackers and part of the beam monitoring were installed within the vac tank. The pt 5 technical teams then succeeded in safely removing the 20t installation tables and their support blocks from beneath the already installed ...

  14. Executive summary

    International Nuclear Information System (INIS)

    2009-01-01

    Prior to the workshop two CSNI/WGHOF surveys were distributed - one addressing regulatory expectations and the other focussing on approaches the licensees use to justify organisational suitability. The regulatory survey requested a brief overview of the situation related to plant organisations in their country - both regulatory expectations and formal requirements. The licensee survey requested information on how they ensure effective organisational suitability, resources and competencies at their plants. The findings from these surveys were used in conjunction with other factors to identify the key issues for the workshop discussions sessions. Although there have been noticeable improvements in recent years in the documentation of the suitability of licensee organisations, almost all regulatory and licensee survey respondents stated that serious questions remain concerning the maturity of the processes to demonstrate the adequacy of the organisational resources and competencies. Other needed improvements identified by licensees include: - indicators for early detection of losses associated with organisational resources and knowledge; - measures for the preservation of specialised knowledge; - refinement of event (root cause) analyses processes to better take into account and identify organisational causes and contributing factors; - better means to evaluate the adequacy of resources. The survey revealed that methods that licensees have found useful to identify and demonstrate the adequacy of the organisational structure, resources and competencies include business oversight process, peer reviews and benchmarking, event and change analysis and establishment of a reference 'organisational baseline'. The workshop participants identified a number of important attributes that characterise a 'good' organisation. One attribute is that the organisation should be open to learning from their experiences and from the experiences of others. This would include taking advantage

  15. Summary Record

    International Nuclear Information System (INIS)

    2008-01-01

    (II-3) - Uncertainty analysis of the steady state benchmark. It should be recognized that the purpose of this benchmark is not only to compare currently available macroscopic approaches but above-all to encourage the development of novel next-generation approaches that focus on more microscopic processes. Thus, the benchmark problem includes both macroscopic and microscopic measurement data. In this context, the sub-channel grade void fraction data are regarded as the macroscopic data and the digitized computer graphic images are the microscopic data. The technical topics to be addressed at the workshop include: - Review of the benchmark activities after the 4. Workshop; - Presentation and discussion of summary of comparisons of final submitted results for Exercise 1 of Phase I (I-1); for Exercise 0 of Phase II (II-0); and for Exercise 1 of Phase II (II-1); - Presentation and discussion of comparison of final submitted results for Exercise 2 of Phase I (I-2); - Presentation and discussion of comparison of final submitted results for Exercise 3 of Phase I (I-3); - Presentation and discussion of comparison of final submitted results for Exercise 2 of Phase II (II-2); - Presentation and discussion of preliminary uncertainty results for Exercise 4 of Phase I (I-4); - Presentation and discussion of preliminary uncertainty results for Exercise 3 of Phase II (II-3); - Preparing a special issue in a journal with participants' BFBT papers; - Defining a work plan and schedule outlining actions to advance the two phases of the benchmark activities

  16. SIG Galileo final converter technical summary report

    International Nuclear Information System (INIS)

    Hinderman, J.D.

    1979-05-01

    The report is primarily concerned with the work performed for DOE on converter development and fabrication for the NASA Galileo Jupiter mission as a DOE prime contractor with interface primarily with Teledyne Energy Systems. The activities reported on were directed toward design, analysis and testing of modules and converters SN-1 thru SN-7 and attendant Quality Control and Reliability effort. Although assembly and testing of SN-1 was not accomplished due to the stop work order, the design was virtually completed and a significant amount of subcontracting and manufacturing of both module and converter components was underway. These subcontracting and manufacturing activities were selectively closed down depending upon degree of completion and material or hardware potential usage in the Technology Program

  17. INDOT Construction Inspection Priorities : Technical Summary

    Science.gov (United States)

    2012-05-01

    In the last decade, the Indiana Department of Transportation (INDOT) increased the number of construction projects funded by capital made available through the leasing of the Indiana Toll Road. However, during the same time period, the level of perso...

  18. Louisiana ITS business plan : technical summary.

    Science.gov (United States)

    2000-03-01

    The objectives are defined under: 1. Development of the plan, which identifies the preferred program of projects and policy initiatives and outlines the purpose, requirements, responsibilities, estimated cost, and implementation schedule for each pla...

  19. AFOSR Technical Report Summaries, October - December 1989

    Science.gov (United States)

    1989-12-01

    0 .0- 1. . - 0. tun a> %.U I L A~ La~ IL’ Ui +IC-~ ~ ~ - 3, - 1C6 .-0t " L VO 00C V .~~@ c 1nV) 13- S0-’ N E-L 15 - In1 In M- V *.inUZ EL- I- m45 v L...3 -0 0Z 0>.CJ - j Li 0 L O.V C) 0 a 1 0/ .Ou. <- C U L- L 0 r- X A L 0 PIx -- 0 n> 0 La -- . < D- 0 zAW m z u 0 . E U Ul I- a . u0-. Im U 1-W0L N U r

  20. Fiber reinforced polymer bridge decks : [technical summary].

    Science.gov (United States)

    2011-01-01

    A number of researchers have addressed the use of Fiber Reinforced Polymer (FRP) deck as a replacement solution for deteriorated bridge decks made of traditional materials. The use of new, advanced materials such as FRP is advantageous when the bridg...

  1. Executive Summary-Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, R. R.

    2004-02-18

    The primary goal since inception of this DOE grant award in 1991 to Wellman Laboratories of Photomedicine, Harvard Medical School, Massachusetts General Hospital, has been to support competitive research fellowships aimed at solving important medical problems, contributing significant new knowledge and/or technology. This approach was taken according to the original intent of the DOE program, to foster excellent centers for research and development of lasers and optics in medicine. Laser photomedicine broadly encompasses optical therapy and optical diagnostics, within any organ system. The research supported clearly reflects this breadth and depth.

  2. Biomass Cookstoves Technical Meeting. Summary Report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2011-05-01

    In regions where biomass is a traditional fuel for cooking, improved cookstoves can enhance indoor air quality, personal health, livelihoods, and the environment—while substantially reducing greenhouse gas (GHG) emissions. Although ongoing efforts have successfully disseminated improved stoves that achieve many of these benefits, substantially greater emissions reductions are needed to comply with international guidelines for indoor air quality and to limit GHG emissions like black carbon.

  3. 2017 Annual Technology Baseline

    Energy Technology Data Exchange (ETDEWEB)

    Cole, Wesley J [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Hand, M. M [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Eberle, Annika [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Beiter, Philipp C [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Kurup, Parthiv [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Turchi, Craig S [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Feldman, David J [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Margolis, Robert M [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Augustine, Chad R [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Maness, Michael [Formerly NREL; O' Connor, Patrick [Oak Ridge National Laboratory

    2018-03-26

    Consistent cost and performance data for various electricity generation technologies can be difficult to find and may change frequently for certain technologies. With the Annual Technology Baseline (ATB), the National Renewable Energy Laboratory annually provides an organized and centralized set of such cost and performance data. The ATB uses the best information from the Department of Energy national laboratories' renewable energy analysts as well as information from the Energy Information Administration for fuel-based technologies. The ATB has been reviewed by experts and it includes the following electricity generation technologies: land-based wind, offshore wind, utility-scale solar photovoltaics (PV), commercial-scale solar PV, residential-scale solar PV, concentrating solar power, geothermal power, hydropower, coal, natural gas, nuclear, and conventional biopower. This webinar presentation introduces the 2017 ATB.

  4. NHTSA's Office of Defects Investigation (ODI) - Technical Service Bulletins System (TSBS) - Downloadable file

    Data.gov (United States)

    Department of Transportation — The Technical Service Bulletins data contains summaries of the Manufacturers' Technical Service Bulletins by single year, make and model. An optional item of Vehicle...

  5. Research Summaries

    Science.gov (United States)

    Brock, Stephen E., Ed.

    2010-01-01

    This column features summaries of research articles from 3 recent crisis management publications. The first, "School Shootings and Counselor Leadership: Four Lessons from the Field" summarized by Kristi Fenning, was conducted as the result of the increased demand for trained crisis personnel on school campuses. Survey participants were…

  6. Conference summaries

    International Nuclear Information System (INIS)

    1986-01-01

    This volume contains conference summaries of the international conference on radioactive waste management of the Canadian Nuclear Society. Topics of discussion include: storage and disposal; hydrogeology and geochemistry; transportation; buffers and backfill; public attitudes; tailings; site investigations and geomechanics; concrete; economics; licensing; matrix materials and container design; durability of fuel; biosphere modelling; radioactive waste processing; and, future options

  7. Executive summary

    NARCIS (Netherlands)

    van Nimwegen, N.; van Nimwegen, N.; van der Erf, R.

    2009-01-01

    The Demography Monitor 2008 gives a concise overview of current demographic trends and related developments in education, the labour market and retirement for the European Union and some other countries. This executive summary highlights the major findings of the Demography Monitor 2008 and further

  8. Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-20

    This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D&D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities.

  9. Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

    International Nuclear Information System (INIS)

    1994-01-01

    This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D ampersand D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities

  10. Biofuels Baseline 2008

    Energy Technology Data Exchange (ETDEWEB)

    Hamelinck, C.; Koper, M.; Berndes, G.; Englund, O.; Diaz-Chavez, R.; Kunen, E.; Walden, D.

    2011-10-15

    The European Union is promoting the use of biofuels and other renewable energy in transport. In April 2009, the Renewable Energy Directive (2009/28/EC) was adopted that set a 10% target for renewable energy in transport in 2020. The directive sets several requirements to the sustainability of biofuels marketed in the frame of the Directive. The Commission is required to report to the European Parliament on a regular basis on a range of sustainability impacts resulting from the use of biofuels in the EU. This report serves as a baseline of information for regular monitoring on the impacts of the Directive. Chapter 2 discusses the EU biofuels market, the production and consumption of biofuels and international trade. It is derived where the feedstock for EU consumed biofuels originally come from. Chapter 3 discusses the biofuel policy framework in the EU and major third countries of supply. It looks at various policy aspects that are relevant to comply with the EU sustainability requirements. Chapter 4 discusses the environmental and social sustainability aspects associated with EU biofuels and their feedstock. Chapter 5 discusses the macro-economic effects that indirectly result from increased EU biofuels consumption, on commodity prices and land use. Chapter 6 presents country factsheets for main third countries that supplied biofuels to the EU market in 2008.

  11. Baseline geochemistry of soil and bedrock Tshirege Member of the Bandelier Tuff at MDA-P

    International Nuclear Information System (INIS)

    Warren, R.G.; McDonald, E.V.; Ryti, R.T.

    1997-08-01

    This report provides baseline geochemistry for soils (including fill), and for bedrock within three specific areas that are planned for use in the remediation of Material Disposal Area P (MDA-P) at Technical Area 16 (TA-16). The baseline chemistry includes leachable element concentrations for both soils and bedrock and total element concentrations for all soil samples and for two selected bedrock samples. MDA-P operated from the early 1950s to 1984 as a landfill for rubble and debris generated by the burning of high explosives (HE) at the TA-16 Burning Ground, HE-contaminated equipment and material, barium nitrate sand, building materials, and trash. The aim of this report is to establish causes for recognizable chemical differences between the background and baseline data sets. In many cases, the authors conclude that recognizable differences represent natural enrichments. In other cases, differences are best attributed to analytical problems. But most importantly, the comparison of background and baseline geochemistry demonstrates significant contamination for several elements not only at the two remedial sites near the TA-16 Burning Ground, but also within the entire region of the background study. This contamination is highly localized very near to the surface in soil and fill, and probably also in bedrock; consequently, upper tolerance limits (UTLs) calculated as upper 95% confidence limits of the 95th percentile are of little value and thus are not provided. This report instead provides basic statistical summaries and graphical comparisons for background and baseline samples to guide strategies for remediation of the three sites to be used in the restoration of MDA-P

  12. Analysis of baseline gene expression levels from ...

    Science.gov (United States)

    The use of gene expression profiling to predict chemical mode of action would be enhanced by better characterization of variance due to individual, environmental, and technical factors. Meta-analysis of microarray data from untreated or vehicle-treated animals within the control arm of toxicogenomics studies has yielded useful information on baseline fluctuations in gene expression. A dataset of control animal microarray expression data was assembled by a working group of the Health and Environmental Sciences Institute's Technical Committee on the Application of Genomics in Mechanism Based Risk Assessment in order to provide a public resource for assessments of variability in baseline gene expression. Data from over 500 Affymetrix microarrays from control rat liver and kidney were collected from 16 different institutions. Thirty-five biological and technical factors were obtained for each animal, describing a wide range of study characteristics, and a subset were evaluated in detail for their contribution to total variability using multivariate statistical and graphical techniques. The study factors that emerged as key sources of variability included gender, organ section, strain, and fasting state. These and other study factors were identified as key descriptors that should be included in the minimal information about a toxicogenomics study needed for interpretation of results by an independent source. Genes that are the most and least variable, gender-selectiv

  13. Baseline conditions at Olkiluoto

    International Nuclear Information System (INIS)

    2003-09-01

    The main purpose of this report is to establish a reference point - defined as the data collected up until the end of year 2002 - for the coming phases of the Finnish spent nuclear fuel disposal programme. The focus is: to define the current surface and underground conditions at the site, both as regards the properties for which a change is expected and for the properties which are of particular interest for long-term safety or environmental impact; to establish, as far as possible, the natural fluctuation of properties that are potentially affected by construction of the underground laboratory, the ONKALO, and to provide references to data on parameters or use in model development and testing and to use models to assist in understanding and interpreting the data. The emphasis of the baseline description is on bedrock characteristics that are relevant to the long-term safety of a spent fuel repository and, hence, to include the hydrogeological, hydrogeochemical, rock mechanical, tectonic and seismic conditions of the site. The construction of the ONKALO will also affect some conditions on the surface, and, therefore, a description of the main characteristics of the nature and the man-made constructions at Olkiluoto is also given. This report is primarily a road map to the available information on the prevailing conditions at the Olkiluoto site and a framework for understanding of data collected. Hence, it refers to numerous available background reports and other archived information produced over the past 20 years or more, and forms a recapitulation and revaluation of the characterisation data of the Olkiluoto site. (orig.)

  14. Mixed waste focus area technical baseline report. Volume 2

    International Nuclear Information System (INIS)

    1997-04-01

    As part of its overall program, the MWFA uses a national mixed waste data set to develop approaches for treating mixed waste that cannot be treated using existing capabilities at DOE or commercial facilities. The current data set was originally compiled under the auspices of the 1995 Mixed Waste Inventory Report. The data set has been updated over the past two years based on Site Treatment Plan revisions and clarifications provided by individual sites. The current data set is maintained by the MWFA staff and is known as MWFA97. In 1996, the MWFA developed waste groupings, process flow diagrams, and treatment train diagrams to systematically model the treatment of all mixed waste in the DOE complex. The purpose of the modeling process was to identify treatment gaps and corresponding technology development needs for the DOE complex. Each diagram provides the general steps needed to treat a specific type of waste. The NWFA categorized each MWFA97 waste stream by waste group, treatment train, and process flow. Appendices B through F provide the complete listing of waste streams by waste group, treatment train, and process flow. The MWFA97 waste strewn information provided in the appendices is defined in Table A-1

  15. Conference Summary

    International Nuclear Information System (INIS)

    Tinkham, M.

    1991-01-01

    This summary will begin with short remarks, trying to recall some of the spirit of the presentations of each of the speakers during the first day, with no attempt at detail or completeness, given the need for a 20:1 compression relative to the original talk. The author hopes these idiosyncratic recollections do not infuriate the speakers too much. Since the speakers on the second day presented such interlocking topics, he simply tries to present some sort of consensus report, to which he adds some comments of his own. The two talks preceding this Summary on the final day dealt with the prospects for applications; since he had no chance to attempt to prepare a proper report on these, he says only a few words about those presentations

  16. Conference summaries

    International Nuclear Information System (INIS)

    1987-01-01

    This volume contains summaries of 28 papers presented at the 27. conference of the Canadian Nuclear Association. These papers discuss the general situation of the Canadian nuclear industry and the CANDU reactor; dialogue with the public; the International Atomic Energy Agency; and economic goals and operating lessons. It also contains summaries of 70 papers presented at the 8. conference of the Canadian Nuclear Society, which discuss plant life extension; safety and the environment; reactor physics; thermalhydraulics; risk assessment; the CANDU spacer location and repositioning project; CANDU operations; safety research after Chernobyl; fuel channels; and nuclear technology developments. The individual papers are also available in INIS-mf--13673 (CNA), and INIS-mf--12909 (CNS). (L.L.)

  17. Summary talk

    International Nuclear Information System (INIS)

    Harari, H.

    1978-10-01

    A general overview is given in this high energy physics conference summary. Quantum chromodynamics as a theory of strong interactions and studied by experimental tests, SU(2) x U(1) theory of weak and electromagnetic interactions and its experimental tests, weak interactions above 100 GeV, simple unification of weak and electromagnetic interactions, and the grand and the ultimate unifications with extended supergravity are discussed. 28 references

  18. Summary talk

    International Nuclear Information System (INIS)

    Johnson, R.C.

    1981-01-01

    In this summary talk some implications of points raised during the Daresbury Study Weekend on heavy-ion reactions are examined and discussed in particular those concerning polarized heavy ions, the connection between analyzing powers and dynamics, transfer reactions, total reaction cross section measurements with polarized beams, and the implications of break-up reaction results for theories of nuclear reactions involving loosely bound projectiles. (U.K.)

  19. Conference summaries

    International Nuclear Information System (INIS)

    1991-01-01

    This volume contains conference summaries for the 31. annual conference of the Canadian Nuclear Association and the 12. annual conference of the Canadian Nuclear Society. Topics of discussion include: reactor physics; thermalhydraulics; industrial irradiation; computer applications; fuel channel analysis; small reactors; severe accidents; fuel behaviour under accident conditions; reactor components, safety related computer software; nuclear fuel management; fuel behaviour and performance; reactor safety; reactor engineering; nuclear waste management; and, uranium mining and processing

  20. Accelerated Best Basis Inventory Baselining Task

    International Nuclear Information System (INIS)

    SASAKI, L.M.

    2001-01-01

    The baselining effort was recently proposed to bring the Best-Basis Inventory (BBI) and Question No.8 of the Tank Interpretive Report (TIR) for all 177 tanks to the current standards and protocols and to prepare a TIR Question No.8 if one is not already available. This plan outlines the objectives and methodology of the accelerated BBI baselining task. BBI baselining meetings held during December 2000 resulted in a revised BBI methodology and an initial set of BBI creation rules to be used in the baselining effort. The objectives of the BBI baselining effort are to: (1) Provide inventories that are consistent with the revised BBI methodology and new BBI creation rules. (2) Split the total tank waste in each tank into six waste phases, as appropriate (Supernatant, saltcake solids, saltcake liquid, sludge solids, sludge liquid, and retained gas). In some tanks, the solids and liquid portions of the sludge and/or saltcake may be combined into a single sludge or saltcake phase. (3) Identify sampling events that are to be used for calculating the BBIs. (4) Update waste volumes for subsequent reconciliation with the Hanlon (2001) waste tank summary. (5) Implement new waste type templates. (6) Include any sample data that might have been unintentionally omitted in the previous BBI and remove any sample data that should not have been included. Sample data to be used in the BBI must be available on TWINS. (7) Ensure that an inventory value for each standard BBI analyte is provided for each waste component. Sample based inventories for supplemental BBI analytes will be included when available. (8) Provide new means and confidence interval reports if one is not already available and include uncertainties in reporting inventory values

  1. Executive summary

    International Nuclear Information System (INIS)

    1981-02-01

    This paper is an 'executive summary' of work undertaken to review proposals for transport, handling and emplacement of high level radioactive wastes in an underground repository, appropriate to the U.K. context, with particular reference to: waste block size and configuration; self-shielded or partially-shielded block; stages of disposal; transportation within the repository; emplacement in vertical holes or horizontal tunnels; repository access by adit, incline or shaft; and costs. The paper contains a section on general conclusions and recommendations. (U.K.)

  2. Summary guidelines

    Energy Technology Data Exchange (ETDEWEB)

    Halsnaes, K.; Painuly, J.P.; Turkson, J.; Meyer, H.J.; Markandya, A.

    1999-09-01

    This document is a summary version of the methodological guidelines for climate change mitigation assessment developed as part of the Global Environment Facility (GEF) project Economics of Greenhouse Gas Limitations; Methodological Guidelines. The objectives of this project have been to develop a methodology, an implementing framework and a reporting system which countries can use in the construction of national climate change mitigation policies and in meeting their future reporting obligations under the FCCC. The methodological framework developed in the Methodological Guidelines covers key economic concepts, scenario building, modelling tools and common assumptions. It was used by several country studies included in the project. (au) 13 refs.

  3. Conference summaries

    International Nuclear Information System (INIS)

    1988-01-01

    This volume contains conference summaries of the 28. annual conference of the Canadian Nuclear Association, and the 9. annual conference of the Canadian Nuclear Society. Topics of discussion include: power reactors; fuel cycles; nuclear power and public understanding; future trends; applications of nuclear technology; CANDU reactors; operational enhancements; design of small reactors; accident behaviour in fuel channels; fuel storage and waste management; reactor commissioning/decommissioning; nuclear safety experiments and modelling; the next generation reactors; advances in nuclear engineering education in Canada; safety of small reactors; current position and improvements of fuel channels; current issues in nuclear safety; and radiation applications - medical and industrial

  4. Baseline Projection Data Book: GRI baseline projection of U.S. Energy Supply and Demand to 2010. 1992 Edition. Volume 1 and Volume 2

    International Nuclear Information System (INIS)

    Holtberg, P.D.; Woods, T.J.; Lihn, M.L.; Koklauner, A.K.

    1992-01-01

    The 1992 Baseline Projection Data Book provides backup data in tabular form for the 1992 GRI Baseline Projection of U.S. Energy Supply and Demand to 2010. Summary tables and data for the residential, commercial, industrial, electric utility, and transportation sectors are presented in the volume

  5. Performance Measurement Baseline Change Request

    Data.gov (United States)

    Social Security Administration — The Performance Measurement Baseline Change Request template is used to document changes to scope, cost, schedule, or operational performance metrics for SSA's Major...

  6. Separations innovative concepts: Project summary

    Energy Technology Data Exchange (ETDEWEB)

    Lee, V.E. (ed.)

    1988-05-01

    This project summary includes the results of 10 innovations that were funded under the US Department's Innovative Concept Programs. The concepts address innovations that can substantially reduce the energy used in industrial separations. Each paper describes the proposed concept, and discusses the concept's potential energy savings, market applications, technical feasibility, prior work and state of the art, and future development needs.

  7. DairyBISS Baseline report

    NARCIS (Netherlands)

    Buizer, N.N.; Berhanu, Tinsae; Murutse, Girmay; Vugt, van S.M.

    2015-01-01

    This baseline report of the Dairy Business Information Service and Support (DairyBISS) project presents the findings of a baseline survey among 103 commercial farms and 31 firms and advisors working in the dairy value chain. Additional results from the survey among commercial dairy farms are

  8. Technical writing versus technical writing

    Science.gov (United States)

    Dillingham, J. W.

    1981-01-01

    Two terms, two job categories, 'technical writer' and 'technical author' are discussed in terms of industrial and business requirements and standards. A distinction between 'technical writing' and technical 'writing' is made. The term 'technical editor' is also considered. Problems inherent in the design of programs to prepare and train students for these jobs are discussed. A closer alliance between industry and academia is suggested as a means of preparing students with competent technical communication skills (especially writing and editing skills) and good technical skills.

  9. Executive Summary

    International Nuclear Information System (INIS)

    2015-01-01

    The 13. Information Exchange Meeting was held in Seoul (Republic of Korea) on 23-26 September 2014, hosted by Seoul National University. The workshop comprised a plenary session on national and international programmes followed by technical sessions and a poster session covering various aspects of P and T. The information exchange meetings on P and T form a part of the NEA programme of work in the field of advanced nuclear fuel cycles. These proceedings include papers presented at the 13. Information Exchange Meeting. The meeting covered strategic and scientific developments in the field of P and T such as: fuel cycle strategies and transition scenarios, the role of P and T in the potential evolution of nuclear energy as part of the future energy mix; radioactive waste management strategies; transmutation fuels and targets; advances in pyro and aqueous separation processes; P and T specific technology requirements (materials, spallation targets, coolants, etc.); transmutation systems: design, performance and safety; impact of P and T on the fuel cycle; fabrication, handling and transportation of transmutation fuels. A total of 103 presentations (39 oral and 64 posters) were discussed among the 110 participants from 19 countries and 2 international organisations. The meeting consisted of one plenary session where national and international programmes were presented followed by 5 technical sessions: - Fuel Cycle Strategies and Transition Scenarios; - Transmutation Systems and Infrastructures; - Waste Management for P and T Scenarios; - Advanced Nuclear Fuel Recycling (Aqueous and Pyro-processing); - Transmutation Fuels and Targets

  10. 75 FR 13680 - Commutation of Sentence: Technical Change

    Science.gov (United States)

    2010-03-23

    ... Sentence: Technical Change AGENCY: Bureau of Prisons, Justice. ACTION: Interim rule. SUMMARY: This document makes a minor technical change to the Bureau of Prisons (Bureau) regulations on sentence commutation to.... Commutation of Sentence: Technical Change This document makes a minor technical change to the Bureau...

  11. IAEA advisory group meeting on technical aspects of atomic and molecular data processing and exchange (15. meeting of the A+M data centres and ALADDIN network). Summary report

    International Nuclear Information System (INIS)

    Stephens, J.A.

    1999-12-01

    The proceedings of the IAEA Advisory Group Meeting on 'Technical Aspects of Atomic and Molecular Data Processing and Exchange' (15th Meeting of A+M Data Centres and ALADDIN Network), held on September 13-14, 1999 in Vienna, Austria are briefly described. The meeting conclusions and recommendations on the priorities in A+M data compilation and evaluation, and on the technical aspects of data processing, exchange, and distribution are also presented. (author)

  12. IAEA advisory group meeting on 'Technical Aspects of Atomic and Molecular Data Processing and Exchange' (14th meeting of the A + M data centres and ALADDIN network). Summary report

    International Nuclear Information System (INIS)

    Stephens, A.

    1998-01-01

    The proceedings of the IAEA Advisory Group Meeting on ''Technical Aspects of Atomic and Molecular Data Processing and Exchange (14th Meeting of A + M Data Centres and ALADDIN Network)'', held on July 21-22, 1997 in Vienna, Austria are briefly described. The meeting conclusions and recommendations on the priorities in A + M data compilation and evaluation, and on the technical aspects of data processing and exchange are also presented. The document includes 15 reports from various Data Centres

  13. IAEA advisory group meeting on technical aspects of atomic and molecular data processing and exchange (16. meeting of the A+M Data Centres and ALADDIN network). Summary report

    Energy Technology Data Exchange (ETDEWEB)

    Stephens, J A [ed.

    2001-12-01

    The proceedings of the IAEA Advisory group meeting on technical aspects of atomic and molecular data processing and exchange (16. meeting of A+M Data centers and ALADDIN Network), held on September 10-11, 2001 in Vienna, Austria are briefly described. The meeting conclusions and recommendations on the priorities in A+M data compilation and evaluation, and on the technical aspects of data processing, exchange and distribution are also presented. (author)

  14. 48 CFR 34.202 - Integrated Baseline Reviews.

    Science.gov (United States)

    2010-10-01

    ... or contractor, and the Government, of the— (1) Ability of the project's technical plan to achieve the... successfully achieve the project schedule objectives; (3) Ability of the Performance Measurement Baseline (PMB... SPECIAL CATEGORIES OF CONTRACTING MAJOR SYSTEM ACQUISITION Earned Value Management System 34.202...

  15. Oscillation Baselining and Analysis Tool

    Energy Technology Data Exchange (ETDEWEB)

    2017-03-27

    PNNL developed a new tool for oscillation analysis and baselining. This tool has been developed under a new DOE Grid Modernization Laboratory Consortium (GMLC) Project (GM0072 - “Suite of open-source applications and models for advanced synchrophasor analysis”) and it is based on the open platform for PMU analysis. The Oscillation Baselining and Analysis Tool (OBAT) performs the oscillation analysis and identifies modes of oscillations (frequency, damping, energy, and shape). The tool also does oscillation event baselining (fining correlation between oscillations characteristics and system operating conditions).

  16. Baseline development, economic risk, and schedule risk: An integrated approach

    International Nuclear Information System (INIS)

    Tonkinson, J.A.

    1994-01-01

    The economic and schedule risks of Environmental Restoration (ER) projects are commonly analyzed toward the end of the baseline development process. Risk analysis is usually performed as the final element of the scheduling or estimating processes for the purpose of establishing cost and schedule contingency. However, there is an opportunity for earlier assessment of risks, during development of the technical scope and Work Breakdown Structure (WBS). Integrating the processes of risk management and baselining provides for early incorporation of feedback regarding schedule and cost risk into the proposed scope of work. Much of the information necessary to perform risk analysis becomes available during development of the technical baseline, as the scope of work and WBS are being defined. The analysis of risk can actually be initiated early on during development of the technical baseline and continue throughout development of the complete project baseline. Indeed, best business practices suggest that information crucial to the success of a project be analyzed and incorporated into project planning as soon as it is available and usable

  17. Making an Impact in the Kurdistan Region--Iraq. Summary of Four Studies to Assess the Present and Future Labor Market, Improve Technical Vocational Education and Training, Reform the Health Sector, and Build Data Collection Capacity. Research Report

    Science.gov (United States)

    Anthony, C. Ross; Constant, Louay; Culbertson, Shelby; Click, Peter; Kumar, Krishna B.; Meili, Robin C.; Moore, Melinda; Shatz, Howard J.; Vernez, Georges

    2015-01-01

    This executive summary describes key results from four studies carried out by the RAND Corporation as part of Phase II of its work for the Kurdistan Regional Government (KRG). The KRG asked RAND to undertake several studies aimed at improving the economic and social development of the Kurdistan Region--Iraq (KRI). RAND's work is intended to help…

  18. Symposium summary

    International Nuclear Information System (INIS)

    Wall, G.

    1990-01-01

    A summary is provided of the issues discussed at the climate change implications for water and ecological resources conference, and recommendations that came out of the conference. The objectives of the meeting were to present and discuss results of recent climate change experiments undertaken in Canada; evaluate a variety of climate models and impact analyses and to develop methods and strategies for future study; and to establish working linkages between modellers and analysts in the fields of climate, hydrology, and ecosystem research, as well as between social scientists and policy makers interested in the implications of climate change. Recommendations were made in the five areas of research, monitoring, risk assessment, policy and information dissemination. Additional research should be undertaken to foster improved understanding of relationships between climate, climate change, and ecological and human processes. A suitable monitoring program, including a national wetlands monitoring program, should be established. Risk assessments should be undertaken to evaluate vulnerabilities of ecosystem components, to assess options, and to provide the information required to develop and implement appropriate policy objectives. The impacts of a range of public policy responses and feedbacks should be assessed. The dissemination of well-targeted and accurate information is vital if basic societal attitudes regarding the value of water and ecosystems are to be changed

  19. Session summaries

    International Nuclear Information System (INIS)

    Sudo, Y.

    2002-01-01

    In the summary session, possible international activities in the field of basic studies on high-temperature engineering were discussed within the framework of the OECD/NEA Nuclear Science Committee (NSC). It was recommended to include topics relevant to fission-product behaviour and safety issues of HTGR in next meeting, in addition to the topics discussed in this meeting. The chairperson of the last session summarised the recommendations to be presented to the NSC into the following five topics as possible international activities: - Basic studies on behaviour of irradiated graphite/carbon and ceramic materials including their composites under both operation and storage conditions. - Development of in-core material characterisation and instrumentation methods. - Improvement in material properties through high-temperature irradiation. - Basic studies on HTGR fuel fabrication and performance including fission-product release. - Basic studies on safety issues of HTGR. It was also recommended that a further information exchange meeting focused on the organisation of the interactive collaboration activity with regard to the above topics be planned in 2003, tentatively in Oarai, Japan. (author)

  20. Theory summary

    International Nuclear Information System (INIS)

    Tang, W.M.

    2001-01-01

    This is a summary of the advances in magnetic fusion energy theory research presented at the 17th International Atomic Energy Agency Fusion Energy Conference from 19 24 October, 1998 in Yokohama, Japan. Theory and simulation results from this conference provided encouraging evidence of significant progress in understanding the physics of thermonuclear plasmas. Indeed, the grand challenge for this field is to acquire the basic understanding that can readily enable the innovations which would make fusion energy practical. In this sense, research in fusion energy is increasingly able to be categorized as fitting well the 'Pasteur's Quadrant' paradigm, where the research strongly couples basic science ('Bohr's Quadrant') to technological impact ('Edison's Quadrant'). As supported by some of the work presented at this conference, this trend will be further enhanced by advanced simulations. Eventually, realistic three-dimensional modeling capabilities, when properly combined with rapid and complete data interpretation of results from both experiments and simulations, can contribute to a greatly enhanced cycle of understanding and innovation. Plasma science theory and simulation have provided reliable foundations for this improved modeling capability, and the exciting advances in high-performance computational resources have further accelerated progress. There were 68 papers presented at this conference in the area of magnetic fusion energy theory

  1. 324 Building Baseline Radiological Characterization

    Energy Technology Data Exchange (ETDEWEB)

    R.J. Reeder, J.C. Cooper

    2010-06-24

    This report documents the analysis of radiological data collected as part of the characterization study performed in 1998. The study was performed to create a baseline of the radiological conditions in the 324 Building.

  2. Baseline restoration using current conveyors

    International Nuclear Information System (INIS)

    Morgado, A.M.L.S.; Simoes, J.B.; Correia, C.M.

    1996-01-01

    A good performance of high resolution nuclear spectrometry systems, at high pulse rates, demands restoration of baseline between pulses, in order to remove rate dependent baseline shifts. This restoration is performed by circuits named baseline restorers (BLRs) which also remove low frequency noise, such as power supply hum and detector microphonics. This paper presents simple circuits for baseline restoration based on a commercial current conveyor (CCII01). Tests were performed, on two circuits, with periodic trapezoidal shaped pulses in order to measure the baseline restoration for several pulse rates and restorer duty cycles. For the current conveyor based Robinson restorer, the peak shift was less than 10 mV, for duty cycles up to 60%, at high pulse rates. Duty cycles up to 80% were also tested, being the maximum peak shift 21 mV. The peak shift for the current conveyor based Grubic restorer was also measured. The maximum value found was 30 mV at 82% duty cycle. Keeping the duty cycle below 60% improves greatly the restorer performance. The ability of both baseline restorer architectures to reject low frequency modulation is also measured, with good results on both circuits

  3. Executive Summary

    International Nuclear Information System (INIS)

    Vari, Anna; Sakuma, Hideki

    2008-01-01

    Within the radioactive waste management community it is now broadly agreed that any decision making will, and should, take place in stages. This allows for better use of current knowledge, for further knowledge to be generated, and for increased opportunity for collective learning and self-training of the various actors. In this process each actor must feel the ability to influence the decision making process, including generating complementary investigations on topics of significance in the field of safety and regarding the long-term impacts. In the technical field of the long-term safety case for disposal it is specifically acknowledged that a safety case (SC) is built in stages, and that it should recognise, at each stage, the open issues and the relevant role of research, development and demonstration (RD and D). It is also acknowledged, in connection with the SC, that stakeholders have a role to play as partners or reviewers and, ultimately, can help to shape the concept of safety. Because today the issue is no longer how to implement an economically-optimal project of waste storage or disposal on a site imposed by the authorities, new challenges are posed to the technical community and to the roles and approaches they take. Important questions are: 1. How to improve on the interaction between science and society, and ensure opportunities for societal direction of RD and D? 2. How to clearly and effectively communicate scientific findings and uncertainties and/or address contradictory views of process participants? Alternatively, how to communicate confidence in the results so far and in the process of acquiring those results? 3. How to encourage 'stretching' of specialists for disclosure of interests, greater transparency, broader dialogue, and to ensure rigour of research programmes? On June 6, 2007 a Topical Session to discuss the above questions was held at OECD NEA. Presentations were invited from delegates of five RWM organisations, including SKI and

  4. The WITCH Model. Structure, Baseline, Solutions.

    Energy Technology Data Exchange (ETDEWEB)

    Bosetti, V.; Massetti, E.; Tavoni, M.

    2007-07-01

    WITCH - World Induced Technical Change Hybrid - is a regionally disaggregated hard link hybrid global model with a neoclassical optimal growth structure (top down) and an energy input detail (bottom up). The model endogenously accounts for technological change, both through learning curves affecting prices of new vintages of capital and through R and D investments. The model features the main economic and environmental policies in each world region as the outcome of a dynamic game. WITCH belongs to the class of Integrated Assessment Models as it possesses a climate module that feeds climate changes back into the economy. In this paper we provide a thorough discussion of the model structure and baseline projections. We report detailed information on the evolution of energy demand, technology and CO2 emissions. Finally, we explicitly quantifiy the role of free riding in determining the emissions scenarios. (auth)

  5. Global Nuclear Energy Partnership Waste Treatment Baseline

    International Nuclear Information System (INIS)

    Gombert, Dirk; Ebert, William; Marra, James; Jubin, Robert; Vienna, John

    2008-01-01

    The Global Nuclear Energy Partnership (GNEP) program is designed to demonstrate that a proliferation-resistant and sustainable integrated nuclear fuel cycle can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline set of waste forms was recommended for the safe disposition of waste streams. Specific waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and expected performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms. (authors)

  6. Global Nuclear Energy Partnership Waste Treatment Baseline

    Energy Technology Data Exchange (ETDEWEB)

    Gombert, Dirk; Ebert, William; Marra, James; Jubin, Robert; Vienna, John [Idaho National laboratory, 2525 Fremont Ave., Idaho Falls, ID 83402 (United States)

    2008-07-01

    The Global Nuclear Energy Partnership (GNEP) program is designed to demonstrate that a proliferation-resistant and sustainable integrated nuclear fuel cycle can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline set of waste forms was recommended for the safe disposition of waste streams. Specific waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and expected performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms. (authors)

  7. Global Nuclear Energy Partnership Waste Treatment Baseline

    Energy Technology Data Exchange (ETDEWEB)

    Dirk Gombert; William Ebert; James Marra; Robert Jubin; John Vienna

    2008-05-01

    The Global Nuclear Energy Partnership program (GNEP) is designed to demonstrate a proliferation-resistant and sustainable integrated nuclear fuel cycle that can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline of waste forms was recommended for the safe disposition of waste streams. Waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness and availability may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms.

  8. Executive summary

    International Nuclear Information System (INIS)

    2002-01-01

    systems. The scope of the workshop comprised reactor physics, fuel performance and fuel material technology, thermal-hydraulics, core behaviour and fuel cycle of advanced reactors with different types of fuels or fuel lattices. Reactor types considered were water-cooled, high-temperature gas-cooled and fast spectrum reactors as well as hybrid reactors with fast and thermal neutron spectra. The emphasis was on innovative concepts and issues related to the reactor and fuel. The workshop concluded with a wide-ranging panel discussion which considered some difficult questions from which it is hoped that some recommendations for future priorities can be derived. A record of the discussion is included at the end of this summary. (author)

  9. Executive Summary

    International Nuclear Information System (INIS)

    2012-01-01

    safety case, and how can the safety case be used to help inform repository design choices? Which are the main open questions and uncertainties? In preparation for the workshop, a review was undertaken to identify and describe relevant examples of the use and functions of cementitious materials in geological disposal concepts from a range of settings. In accordance with the intent of the workshop, the review covered geological disposal concepts for high-level wastes (HLW) and spent fuel, as well as for intermediate-level wastes (ILW) and their equivalents. Abstracts and supporting papers for oral presentations and posters presented at the workshop are included as Appendices C and D. This report provides a synthesis of the workshop, and summarises its main results and findings. The structure of this report follows the workshop agenda: - Section 2 summarises plenary and working group discussions on the uses, functions and evolution of cementitious materials in geological disposal, and highlights key aspects and discussions points. - Section 3 summarises plenary and working group discussions on interactions of cementitious materials with other disposal system components, and highlights key aspects and discussions points. - Section 4 summarises the workshop session on the integration of issues related to cementitious materials using the safety case. - Section 5 presents the main conclusions from the workshop. - Section 6 contains a list of references. - Appendix A presents the workshop agenda. - Appendix B contains the abstracts and, where provided, technical papers supporting oral presentations at the workshop. - Appendix C contains the abstracts and, where provided, technical papers supporting posters presented at the workshop. - Appendix D records the workshop participants and the composition of the working groups

  10. Executive summary

    International Nuclear Information System (INIS)

    2014-01-01

    The workshop included an opening session, six sessions with participant presentations followed by short discussion, and two facilitated discussion sessions. The contributions presented were devoted to new methodological developments, projects with external hazards analysis activities, interesting aspects of external hazards analysis and expected challenges for future analyses. The contributions presented and the discussions organized during the workshop provided valuable input for strengthening the role of WGRISK in supporting the development and application of probabilistic safety assessment and risk-oriented decision making methods in the area of external hazards. The workshop supported the key general objectives of collecting and exchanging information from OECD member states on the methods and approaches used in probabilistic safety assessment in this area. The focus of the workshop was on external events PSA for nuclear power plants, including all modes of operation. The workshop scope was generally limited to external, natural hazards, including those hazards where the distinction between natural and man-made hazards is not sharp (e.g., external floods caused by dam failures). The participation was open to experts from regulatory authorities and their technical support organizations, research organizations, utilities, nuclear power plant (NPP) designers and vendors, industry associations and observers from OECD NEA member countries. The Background, Objectives, Organization, and Topics of the Workshop are presented in chapter 1. The WGRISK activities preceding the workshop and leading to the decision to organize it are described in Chapter 2. The detailed information about the presentations, discussions, and results of the workshop is presented in Chapter 3. Detailed information about the conclusions made during the workshop is presented in Chapter 4. The list of participants, the workshop agenda and the papers/presentations are attached in the appendixes

  11. Developing RESRAD-BASELINE for environmental baseline risk assessment

    International Nuclear Information System (INIS)

    Cheng, Jing-Jy.

    1995-01-01

    RESRAD-BASELINE is a computer code developed at Argonne developed at Argonne National Laboratory for the US Department of Energy (DOE) to perform both radiological and chemical risk assessments. The code implements the baseline risk assessment guidance of the US Environmental Protection Agency (EPA 1989). The computer code calculates (1) radiation doses and cancer risks from exposure to radioactive materials, and (2) hazard indexes and cancer risks from exposure to noncarcinogenic and carcinogenic chemicals, respectively. The user can enter measured or predicted environmental media concentrations from the graphic interface and can simulate different exposure scenarios by selecting the appropriate pathways and modifying the exposure parameters. The database used by PESRAD-BASELINE includes dose conversion factors and slope factors for radionuclides and toxicity information and properties for chemicals. The user can modify the database for use in the calculation. Sensitivity analysis can be performed while running the computer code to examine the influence of the input parameters. Use of RESRAD-BASELINE for risk analysis is easy, fast, and cost-saving. Furthermore, it ensures in consistency in methodology for both radiological and chemical risk analyses

  12. Guam Initial Technical Assessment Report

    Energy Technology Data Exchange (ETDEWEB)

    Baring-Gould, I.; Conrad, M.; Haase, S.; Hotchkiss, E.; McNutt, P.

    2011-04-01

    Under an interagency agreement, funded by the Department of Interior's (DOI) Office of Insular Affairs (OIA), the National Renewable Energy Laboratory (NREL) was tasked to deliver technical assistance to the island of Guam by conducting an island initial technical assessment that would lay out energy consumption and production data and establish a baseline. This assessment will be used to conduct future analysis and studies by NREL that will estimate energy efficiency and renewable energy potential for the island of Guam.

  13. Integrating risk management into the baselining process

    International Nuclear Information System (INIS)

    Jennett, N.; Tonkinson, A.

    1994-01-01

    These processes work together in building the project (comprised of the technical, schedule, and cost baselines) against which performance is measured and changes to the scope, schedule and cost of a project are managed and controlled. Risk analysis is often performed as the final element of the scheduling or estimating processes, a precursor to establishing cost and schedule contingency. However, best business practices dictate that information that may be crucial to the success of a project be analyzed and incorporated into project planning as soon as it is available and usable. The purpose or risk management is not to eliminate risk. Neither is it intended to suggest wholesale re-estimating and re-scheduling of a project. Rather, the intent is to make provisions to reduce and control the schedule and/or cost ramifications of risk by anticipating events and conditions that cannot be reliably planned for and which have the potential to negatively impact accomplishment of the technical objectives and requirements of the project

  14. Gradual linguistic summaries

    NARCIS (Netherlands)

    Wilbik, A.M.; Kaymak, U.; Laurent, A.; Strauss, O.; Bouchon-Meunier, xx

    2014-01-01

    In this paper we propose a new type of protoform-based linguistic summary – the gradual summary. This new type of summaries aims in capturing the change over some time span. Such summaries can be useful in many domains, for instance in economics, e.g., "prices of X are getting smaller" in eldercare,

  15. Imagining Technicities

    DEFF Research Database (Denmark)

    Liboriussen, Bjarke; Plesner, Ursula

    2011-01-01

    to the elements of taste and skill. In the final analysis those references were synthesized as five imagined technicities: the architect, the engineer, the client, the Chinese, and the Virtual World native. Because technicities are often assumed and rarely discussed as actants who influence practice, their role......, this article focuses on innovative uses of virtual worlds in architecture. We interviewed architects, industrial designers and other practitioners. Conceptually supported by an understanding of technicity found in Cultural Studies, the interviews were then coded with a focus on interviewees’ references...... in cooperation and development of ICTs seems to pass unnoticed. However, since they are aligned into ICTs, technicities impact innovation....

  16. Summary Record

    International Nuclear Information System (INIS)

    2008-01-01

    of the steady state critical power benchmark. The purpose of this benchmark is not only the comparison of currently available macroscopic approaches but above-all to encourage the development of novel next-generation approaches that focus on more microscopic processes. Thus, the benchmark problem includes both macroscopic and microscopic measurement data. In this context, the sub-channel grade void fraction data are regarded as the macroscopic data and the digitized computer graphic images are the microscopic data. The technical topics addressed at the workshop include: - Review of the benchmark activities after the 2. Workshop; - Discussion of the final version of the specifications and spacer's dimensions; - Presentation and discussion of modelling issues and comparison of submitted results for Exercise 1 of Phase I (I-1); - Presentation and discussion of modelling issues and comparison of submitted results for Exercise 2 of Phase I (I-2); - Presentation and discussion of modelling issues and comparison of submitted results for Exercise 0, Phase II (II-0); - Presentation and discussion of modelling issues and comparison of submitted results for Exercise 1, Phase II (II-1); - Discussion of the requested output and templates for submitting results for Exercises 3 and 4 of Phase I (I-3 and I-4), and Exercise 2 of Phase II (II-2); - Discussion of Exercise 4 of Phase I (uncertainty analysis of I-1) and discussion of the introduction of Exercise 3 of Phase II (II-3) uncertainty analysis of II-1; - Defining a work plan and schedule outlining actions to progress the two phases of the benchmark activities

  17. Summary record

    International Nuclear Information System (INIS)

    2009-01-01

    ; Exercise 3 (II-3) - Uncertainty analysis of the steady critical power benchmark. It should be recognized that the purpose of this benchmark is not only to compare currently available macroscopic approaches but above-all to encourage the development of novel next-generation approaches that focus on more microscopic processes. Thus, the benchmark problem includes both macroscopic and microscopic measurement data. In this context, the sub-channel grade void fraction data are regarded as the macroscopic data and the digitized computer graphic images are the microscopic data. The technical topics addressed at the workshop included: - Review of the benchmark activities after the 5. Workshop - Discussion of the report on Phase I - Participants' presentations on their models and results for Exercises I-1, I-2 and I-3 - Discussion of the report on Phase II - Participants' presentations on their models and results for Exercises II-0, II-1 and II-2 - Presentation and discussion of the results submitted for the uncertainty analysis exercises - Participants' presentations on their models and results for Exercises I-4 and II-3 - Introduction and presentation of the new OECD benchmark based on NUPEC PWR Sub-channel and Bundle Tests (PSBT) (as follow-up benchmark activities of the OECD/NRC BFBT benchmark): database, specification and schedule. - Status of the NED special issue with participants' BFBT papers - Defining a work plan and schedule outlining actions to progress the two phases of the benchmark activities

  18. Summary Record

    International Nuclear Information System (INIS)

    2007-01-01

    ; Exercise 3 (II-3): Uncertainty analysis of the steady critical power benchmark. It should be recognized that the purpose of this benchmark is not only to compare currently available macroscopic approaches but above-all to encourage the development of novel next-generation approaches that focus on more microscopic processes. Thus, the benchmark problem includes both macroscopic and microscopic measurement data. In this context, the sub-channel grade void fraction data are regarded as the macroscopic data and the digitized computer graphic images are the microscopic data. The technical topics addressed at the workshop included: - Review of the benchmark activities after the 3. Workshop; - Discussion of the draft version of Volume II of the specifications on uncertainty analysis exercises; - Presentation and discussion of comparison of final submitted results for Exercise 1 of Phase I (I-1); - Presentation and discussion of comparison of final submitted results for Exercise 0, Phase II (II-0); - Presentation and discussion of comparison of final submitted results for Exercise 1, Phase II (II-1); - Presentation and discussion of modelling issues and comparison of submitted results for Exercise 2, Phase I (I-2); - Presentation and discussion of modelling issues and comparison of submitted results for Exercise 3, Phase I (I-3); - Presentation and discussion of modelling issues and comparison of submitted results for Exercise 2, Phase II (II-2); - Discussion of the requested output and templates for submitting results for Exercise 4 of Phase I (I-4), and Exercise 3 of Phase II (II-3); - Defining a work plan and schedule outlining actions to advance the two phases of the benchmark activities

  19. Executive summary

    International Nuclear Information System (INIS)

    2015-01-01

    routes to fabricate materials and components for innovative nuclear systems. The 'ions vs. neutron irradiation' topic focused on specific irradiation comparisons including mechanical properties and microstructural effects caused by ion or neutron irradiation. Comparative irradiation studies on a common material were also welcome. Fuel-cladding interaction was not covered in this edition of the workshop. The workshop received 74 abstracts, and was scheduled with 5 invited talks, 27 oral presentations and 2 poster sessions (42 posters) from 75 registered participants. However, it was necessary to reorganise the programme at extremely short notice to take into account the effects of the unexpected US government shutdown and the constraints this imposed on the workshop. In total, 38 participants from 12 countries and 2 international organisations attended, and the final number of presentations amounted to 51 (22 oral presentations and 29 posters). The re-scheduled workshop opened with the welcome address by S. Cornet on behalf of the OECD Nuclear Energy Agency followed by technical sessions: Session I: Overview on programmes and metal alloys. Session II: Metal alloys. Session III: Novel pathways. Session IV: Ceramic composites, ions vs. neutrons and general

  20. Long baseline neutrino oscillation experiments

    International Nuclear Information System (INIS)

    Gallagher, H.

    2006-01-01

    In this paper I will review briefly the experimental results which established the existence of neutrino mixing, the current generation of long baseline accelerator experiments, and the prospects for the future. In particular I will focus on the recent analysis of the MINOS experiment. (author)

  1. THE 2014 ALMA LONG BASELINE CAMPAIGN: AN OVERVIEW

    Energy Technology Data Exchange (ETDEWEB)

    Partnership, ALMA [Astrophysics Research Institute, Liverpool John Moores University, IC2, Liverpool Science Park, 146 Brownlow Hill, Liverpool L3 5RF (United Kingdom); Fomalont, E. B.; Vlahakis, C.; Corder, S.; Remijan, A.; Barkats, D.; Dent, W. R. F.; Phillips, N.; Cox, P.; Hales, A. S. [Joint ALMA Observatory, Alonso de Córdova 3107, Vitacura, Santiago (Chile); Lucas, R. [Institut de Planétologie et d’Astrophysique de Grenoble (UMR 5274), BP 53, F-38041 Grenoble Cedex 9 (France); Hunter, T. R.; Brogan, C. L.; Amestica, R.; Cotton, W. [National Radio Astronomy Observatory, 520 Edgemont Road, Charlottesville, VA 22903 (United States); Asaki, Y. [National Astronomical Observatory of Japan, 2-21-1 Osawa, Mitaka, Tokyo 181-8588 (Japan); Matsushita, S. [Institute of Astronomy and Astrophysics, Academia Sinica, P.O. Box 23-141, Taipei 106, Taiwan (China); Hills, R. E. [Astrophysics Group, Cavendish Laboratory, JJ Thomson Avenue, Cambridge CB3 0HE (United Kingdom); Richards, A. M. S. [Jodrell Bank Centre for Astrophysics, School of Physics and Astronomy, University of Manchester, Oxford Road, Manchester M13 9PL (United Kingdom); Broguiere, D., E-mail: efomalon@nrao.edu [Institut de Radioastronomie Millime´trique (IRAM), 300 rue de la Piscine, Domaine Universitaire, F-38406 Saint Martin d’Hères (France); and others

    2015-07-20

    A major goal of the Atacama Large Millimeter/submillimeter Array (ALMA) is to make accurate images with resolutions of tens of milliarcseconds, which at submillimeter (submm) wavelengths requires baselines up to ∼15 km. To develop and test this capability, a Long Baseline Campaign (LBC) was carried out from 2014 September to late November, culminating in end-to-end observations, calibrations, and imaging of selected Science Verification (SV) targets. This paper presents an overview of the campaign and its main results, including an investigation of the short-term coherence properties and systematic phase errors over the long baselines at the ALMA site, a summary of the SV targets and observations, and recommendations for science observing strategies at long baselines. Deep ALMA images of the quasar 3C 138 at 97 and 241 GHz are also compared to VLA 43 GHz results, demonstrating an agreement at a level of a few percent. As a result of the extensive program of LBC testing, the highly successful SV imaging at long baselines achieved angular resolutions as fine as 19 mas at ∼350 GHz. Observing with ALMA on baselines of up to 15 km is now possible, and opens up new parameter space for submm astronomy.

  2. THE 2014 ALMA LONG BASELINE CAMPAIGN: AN OVERVIEW

    International Nuclear Information System (INIS)

    Partnership, ALMA; Fomalont, E. B.; Vlahakis, C.; Corder, S.; Remijan, A.; Barkats, D.; Dent, W. R. F.; Phillips, N.; Cox, P.; Hales, A. S.; Lucas, R.; Hunter, T. R.; Brogan, C. L.; Amestica, R.; Cotton, W.; Asaki, Y.; Matsushita, S.; Hills, R. E.; Richards, A. M. S.; Broguiere, D.

    2015-01-01

    A major goal of the Atacama Large Millimeter/submillimeter Array (ALMA) is to make accurate images with resolutions of tens of milliarcseconds, which at submillimeter (submm) wavelengths requires baselines up to ∼15 km. To develop and test this capability, a Long Baseline Campaign (LBC) was carried out from 2014 September to late November, culminating in end-to-end observations, calibrations, and imaging of selected Science Verification (SV) targets. This paper presents an overview of the campaign and its main results, including an investigation of the short-term coherence properties and systematic phase errors over the long baselines at the ALMA site, a summary of the SV targets and observations, and recommendations for science observing strategies at long baselines. Deep ALMA images of the quasar 3C 138 at 97 and 241 GHz are also compared to VLA 43 GHz results, demonstrating an agreement at a level of a few percent. As a result of the extensive program of LBC testing, the highly successful SV imaging at long baselines achieved angular resolutions as fine as 19 mas at ∼350 GHz. Observing with ALMA on baselines of up to 15 km is now possible, and opens up new parameter space for submm astronomy

  3. Fuel Assembly Damping Summary

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kanghee; Kang, Heungseok; Oh, Dongseok; Yoon, Kyungho; Kim, Hyungkyu; Kim, Jaeyong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    This paper summary the fuel assembly damping data in air/in still water/under flow, released from foreign fuel vendors, compared our data with the published data. Some technical issues in fuel assembly damping measurement testing are also briefly discussed. Understanding of each fuel assembly damping mechanisms according to the surrounding medium and flow velocity can support the fuel design improvement in fuel assembly dynamics and structural integrity aspect. Because the upgraded requirements of the newly-developed advanced reactor system will demands to minimize fuel design margin in integrity evaluation, reduction in conservatism of fuel assembly damping can contribute to alleviate the fuel design margin for sure. Damping is an energy dissipation mechanism in a vibrating mechanical structure and prevents a resonant structure from having infinite vibration amplitudes. The sources of fuel assembly damping are various from support friction to flow contribution, and it can be increased by the viscosity or drag of surrounding fluid medium or the average velocity of water flowing. Fuel licensing requires fuel design evaluation in transient or accidental condition. Dynamic response analysis of fuel assembly is to show fuel integrity and requires information on assembly-wise damping in dry condition and under wet or water flowing condition. However, damping measurement test for the full-scale fuel assembly prototype is not easy to carry out because of the scale (fuel prototype, test facility), unsteadiness of test data (scattering, random sampling and processing), instrumentation under water flowing (water-proof response measurement), and noise. LWR fuel technology division in KAERI is preparing the infra structure for damping measurement test of full-scale fuel assembly, to support fuel industries and related research activities. Here is a preliminary summary of fuel assembly damping, published in the literature. Some technical issues in fuel assembly damping

  4. Unresolved safety issues summary: aqua book

    International Nuclear Information System (INIS)

    1982-06-01

    The unresolved safety issues summary is designed to provide the management of the Nuclear Regulatory Commission with a quarterly overview of the progress and plans for completion of generic tasks addressing unresolved safety issues reported to Congress pursuant to Section 210 of the Energy Reorganization Act of 1974 as amended. This summary utilizes data collected from the Office of Nuclear Reactor Regulation, Office of Nuclear Regulatory Research, and the National Laboratories and is prepared by the Office of Resource Management. The schedules in this book include a milestone at the end of each action plan which represents the initiation of the implementation process both with respect to incorporation of the technical resolution in the NRC official guidance or requirements and also the application of changes to individual operating plants. The progress and status for implementation of unresolved safety issues for which a technical resolution has been completed are reported specifically in a separate table provided in this summary

  5. Summary record

    International Nuclear Information System (INIS)

    2007-01-01

    encouragement to developing novel next-generation approaches that focus on more microscopic processes. Thus, the benchmark problem includes both macroscopic and microscopic measurement data. In this context, the sub-channel grade void fraction data are regarded as the macroscopic data and the digitized computer graphic images are the microscopic data. The meeting was organized around the discussion of the Benchmark Specifications, as well as the presentation and discussion of modelling issues and preliminary results for Exercises 1 and 2 of Phase 1, and Exercise 1 of Phase 2. At the first workshop of the OECD/NRC BFBT Benchmark BFBT-1 - a schedule for benchmark activities was accepted by the participants (see NEA/NSC/DOC (2004)15). According to this schedule the participants were requested to submit their results for Exercises 1 of Phase 1 and Phase 2 by April 30, 2005, which was postponed because of the delay in issuing the BFBT Benchmark Specifications. The Version 2 of the Specifications was distributed in May 2005 and the participants were requested to review the Specifications and were encouraged to start modelling of Exercises 1 of Phase 1 and Phase 2 as well as Exercise 2 of Phase 2. This was beneficial for the discussions at the 2. Workshop where the participants were requested to present any available preliminary results, for the exercises of both phases. Presentations on related experience in BWR sub-channel modelling as well as on CFD modelling were also encouraged. The technical topics, which were presented and discussed at the BFBT-2 workshop, are as follows: Review of the benchmark activities after the first Workshop; Detailed discussion of test facility, test conditions and measurement techniques; Discussion of the complete test data provided on the CD-ROM to the participants' key for using the data and format of the data; Discussion of the Benchmark Specifications and how the benchmark cases have been selected; Presentation and discussion of modelling issues and

  6. Baseline budgeting for continuous improvement.

    Science.gov (United States)

    Kilty, G L

    1999-05-01

    This article is designed to introduce the techniques used to convert traditionally maintained department budgets to baseline budgets. This entails identifying key activities, evaluating for value-added, and implementing continuous improvement opportunities. Baseline Budgeting for Continuous Improvement was created as a result of a newly named company president's request to implement zero-based budgeting. The president was frustrated with the mind-set of the organization, namely, "Next year's budget should be 10 to 15 percent more than this year's spending." Zero-based budgeting was not the answer, but combining the principles of activity-based costing and the Just-in-Time philosophy of eliminating waste and continuous improvement did provide a solution to the problem.

  7. 75 FR 30804 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2010-06-02

    ... DEPARTMENT OF ENERGY Biomass Research and Development Technical Advisory Committee AGENCY.... SUMMARY: This notice announces an open meeting of the Biomass Research and Development Technical Advisory... public are welcome to observe the business of the Biomass Research and Development Technical Advisory...

  8. 75 FR 11526 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2010-03-11

    ... DEPARTMENT OF ENERGY Biomass Research and Development Technical Advisory Committee AGENCY.... SUMMARY: This notice announces an open meeting of the Biomass Research and Development Technical Advisory... public are welcome to observe the business of the Biomass Research and Development Technical Advisory...

  9. 75 FR 56525 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2010-09-16

    ... DEPARTMENT OF ENERGY Biomass Research and Development Technical Advisory Committee AGENCY.... SUMMARY: This notice announces an open meeting of the Biomass Research and Development Technical Advisory... business of the Biomass Research and Development Technical Advisory Committee. To attend the meeting and/or...

  10. Hanford spent fuel inventory baseline

    International Nuclear Information System (INIS)

    Bergsman, K.H.

    1994-01-01

    This document compiles technical data on irradiated fuel stored at the Hanford Site in support of the Hanford SNF Management Environmental Impact Statement. Fuel included is from the Defense Production Reactors (N Reactor and the single-pass reactors; B, C, D, DR, F, H, KE and KW), the Hanford Fast Flux Test Facility Reactor, the Shipping port Pressurized Water Reactor, and small amounts of miscellaneous fuel from several commercial, research, and experimental reactors

  11. Logistics Operations Management Center: Maintenance Support Baseline (LOMC-MSB)

    Science.gov (United States)

    Kurrus, R.; Stump, F.

    1995-01-01

    The Logistics Operations Management Center Maintenance Support Baseline is defined. A historical record of systems, applied to and deleted from, designs in support of future management and/or technical analysis is provided. All Flight elements, Ground Support Equipment, Facility Systems and Equipment and Test Support Equipment for which LOMC has responsibilities at Kennedy Space Center and other locations are listed. International Space Station Alpha Program documentation is supplemented. The responsibility of the Space Station Launch Site Support Office is established.

  12. Mycoplasma genitalium From Basic Science to Public Health: Summary of the Results From a National Institute of Allergy and Infectious Disesases Technical Consultation and Consensus Recommendations for Future Research Priorities.

    Science.gov (United States)

    Martin, David H; Manhart, Lisa E; Workowski, Kimberly A

    2017-07-15

    This article lays out the research priorities for Mycoplasma genitalium research agreed upon by the participants in a 2016 National Institutes of Allergy and Infectious Diseases-funded Technical Consultation focused on this organism. The state of current knowledge concerning the microbiology, epidemiology, clinical manifestations of infection, treatment, and public health significance of M. genitalium reviewed at the meeting is described in detail in the individual articles included in this supplemental edition of the Journal of Infectious Diseases. Here we summarize the points made in these articles most relevant to the formulation of the research priorities listed in this article. The most important recommendation resulting from this Technical Consultation is the initiation of clinical trials designed to determine definitively whether screening for and treatment of M. genitalium infections in women and their sexual partners improve reproductive health in women and/or prevent human immunodeficiency virus transmission. © The Author 2017. Published by Oxford University Press for the Infectious Diseases Society of America. All rights reserved. For permissions, e-mail: journals.permissions@oup.com.

  13. Technical Network

    CERN Multimedia

    2007-01-01

    In order to optimize the management of the Technical Network (TN), to ease the understanding and purpose of devices connected to the TN, and to improve security incident handling, the Technical Network Administrators and the CNIC WG have asked IT/CS to verify the "description" and "tag" fields of devices connected to the TN. Therefore, persons responsible for systems connected to the TN will receive email notifications from IT/CS asking them to add the corresponding information in the network database. Thank you very much for your cooperation. The Technical Network Administrators & the CNIC WG

  14. Technical Network

    CERN Multimedia

    2007-01-01

    In order to optimise the management of the Technical Network (TN), to facilitate understanding of the purpose of devices connected to the TN and to improve security incident handling, the Technical Network Administrators and the CNIC WG have asked IT/CS to verify the "description" and "tag" fields of devices connected to the TN. Therefore, persons responsible for systems connected to the TN will receive e-mails from IT/CS asking them to add the corresponding information in the network database at "network-cern-ch". Thank you very much for your cooperation. The Technical Network Administrators & the CNIC WG

  15. Fusion Engineering Device. Volume 1. Mission and program summary

    International Nuclear Information System (INIS)

    1981-10-01

    This volume presents, in summary form, a recommended approach to implementing the Magnetic Fusion Energy Engineering Act of 1980. These recommendations constitute the findings of the FED Technical Management Board (TMB). The TMB and the affiliated technical managers gave particular scrutiny to elucidating the role of FED in fusion development and to defining the device mission

  16. Office of Geologic Repositories program baseline procedures notebook (OGR/B-1)

    International Nuclear Information System (INIS)

    1986-06-01

    Baseline management is typically applied to aid in the internal control of a program by providing consistent programmatic direction, control, and surveillance to an evolving system development. This fundamental concept of internal program control involves the establishment of a baseline to serve as a point of departure for consistent technical program coordination and to control subsequent changes from that baseline. The existence of a program-authorized baseline ensures that all participants are working to the same ground rules. Baseline management also ensures that, once the baseline is defined, changes are assessed and approved by a process which ensures adequate consideration of overall program impact. Baseline management also includes the consideration of examptions from the baseline. The process of baseline management continues through all the phases of an evolving system development program. As the Program proceeds, there will be a progressive increase in the data contained in the baseline documentation. Baseline management has been selected as a management technique to aid in the internal control of the Office of Geologic Repositories (OGR) program. Specifically, an OGR Program Baseline, including technical and programmatic requirements, is used for program control of the four Mined Geologic Disposal System field projects, i.e., Basalt Waste Isolation Project, Nevada Nuclear Waste Storage Investigation, Salt Repository Project and Crystalline Repository Project. This OGR Program Baseline Procedures Notebook provides a description of the baseline mwanagement concept, establishes the OGR Program baseline itself, and provides procedures to be followed for controlling changes to that baseline. The notebook has a controlled distribution and will be updated as required

  17. Integrated Baseline Review (IBR) Handbook

    Science.gov (United States)

    Fleming, Jon F.; Terrell, Stefanie M.

    2018-01-01

    The purpose of this handbook is intended to be a how-to guide to prepare for, conduct, and close-out an Integrated Baseline Review (IBR). It discusses the steps that should be considered, describes roles and responsibilities, tips for tailoring the IBR based on risk, cost, and need for management insight, and provides lessons learned from past IBRs. Appendices contain example documentation typically used in connection with an IBR. Note that these appendices are examples only, and should be tailored to meet the needs of individual projects and contracts.

  18. Environmental Baseline File National Transportation

    International Nuclear Information System (INIS)

    Harris, M.

    1999-01-01

    This Environmental Baseline File summarizes and consolidates information related to the national-level transportation of commercial spent nuclear fuel. Topics addressed include: shipments of commercial spent nuclear fuel based on mostly truck and mostly rail shipping scenarios; transportation routing for commercial spent nuclear fuel sites and DOE sites; radionuclide inventories for various shipping container capacities; transportation routing; populations along transportation routes; urbanized area population densities; the impacts of historical, reasonably foreseeable, and general transportation; state-level food transfer factors; Federal Guidance Report No. 11 and 12 radionuclide dose conversion factors; and national average atmospheric conditions

  19. Baseline LAW Glass Formulation Testing

    International Nuclear Information System (INIS)

    Kruger, Albert A.; Mooers, Cavin; Bazemore, Gina; Pegg, Ian L.; Hight, Kenneth; Lai, Shan Tao; Buechele, Andrew; Rielley, Elizabeth; Gan, Hao; Muller, Isabelle S.; Cecil, Richard

    2013-01-01

    The major objective of the baseline glass formulation work was to develop and select glass formulations that are compliant with contractual and processing requirements for each of the LAW waste streams. Other objectives of the work included preparation and characterization of glasses with respect to the properties of interest, optimization of sulfate loading in the glasses, evaluation of ability to achieve waste loading limits, testing to demonstrate compatibility of glass melts with melter materials of construction, development of glass formulations to support ILAW qualification activities, and identification of glass formulation issues with respect to contract specifications and processing requirements

  20. Alpine Windharvest: development of information base regarding potentials and the necessary technical, legal and socio-economic conditions for expanding wind energy in the Alpine Space - CFD modelling evaluation - Summary of WindSim CFD modelling procedure and validation

    Energy Technology Data Exchange (ETDEWEB)

    Schaffner, B.; Cattin, R. [Meteotest, Berne (Switzerland)

    2005-07-01

    This report presents the development work carried out by the Swiss meteorology specialists of the company METEOTEST as part of a project carried out together with the Swiss wind-energy organisation 'Suisse Eole'. The framework for the project is the EU Interreg IIIB Alpine Space Programme, a European Community Initiative Programme funded by the European Regional Development Fund. The project investigated the use of digital relief-analysis. The report describes the development of a basic information system to aid the investigation of the technical, legal and socio-economical conditions for the use of wind energy in the alpine area. The report deals with the use of computational fluid dynamics and wind simulation modelling techniques and their validation. Recommendations on the use of the results are made.

  1. Safety Evaluation of the ESP Sludge Washing Baselines Runs. Revision 1

    International Nuclear Information System (INIS)

    Gupta, M.K.

    1994-08-01

    The purpose is to provide the technical basis for the evaluation of Unreviewed Safety Question for the Extended Sludge Processing (ESP) Sludge Washing Baseline Runs. The Baseline runs are necessary: to ascertain the mechanical fitness of the equipment and modifications not operated since 1988 and to resolve technical questions associated with process control; i.e., sludge suspension, sludge settling, heat transfer, and temperature control. These issues need to be resolved prior to resumption of normal ESP operations. The equipment used for the Baseline runs are Tanks 42H and 51H and their associated equipment

  2. System for technical innovation support

    International Nuclear Information System (INIS)

    2011-08-01

    This book lists field of support system, which includes tax, development work, basic research project, industrial technology, information and communications field, energy field, part and materials field, local industry, the small and medium business such as technical development field, and industry-university collaboration like summary of investment and financing support and guarantee, support of manpower such as brain pool and contact Korea, support of technique like development technology and strategy for patent, support on certification such as company and technical goods, purchase support.

  3. FED baseline engineering studies report

    Energy Technology Data Exchange (ETDEWEB)

    Sager, P.H.

    1983-04-01

    Studies were carried out on the FED Baseline to improve design definition, establish feasibility, and reduce cost. Emphasis was placed on cost reduction, but significant feasibility concerns existed in several areas, and better design definition was required to establish feasibility and provide a better basis for cost estimates. Design definition and feasibility studies included the development of a labyrinth shield ring concept to prevent radiation streaming between the torus spool and the TF coil cryostat. The labyrinth shield concept which was developed reduced radiation streaming sufficiently to permit contact maintenance of the inboard EF coils. Various concepts of preventing arcing between adjacent shield sectors were also explored. It was concluded that installation of copper straps with molybdenum thermal radiation shields would provide the most reliable means of preventing arcing. Other design studies included torus spool electrical/structural concepts, test module shielding, torus seismic response, poloidal conditions in the magnets, disruption characteristics, and eddy current effects. These additional studies had no significant impact on cost but did confirm the feasibility of the basic FED Baseline concept.

  4. FED baseline engineering studies report

    International Nuclear Information System (INIS)

    Sager, P.H.

    1983-04-01

    Studies were carried out on the FED Baseline to improve design definition, establish feasibility, and reduce cost. Emphasis was placed on cost reduction, but significant feasibility concerns existed in several areas, and better design definition was required to establish feasibility and provide a better basis for cost estimates. Design definition and feasibility studies included the development of a labyrinth shield ring concept to prevent radiation streaming between the torus spool and the TF coil cryostat. The labyrinth shield concept which was developed reduced radiation streaming sufficiently to permit contact maintenance of the inboard EF coils. Various concepts of preventing arcing between adjacent shield sectors were also explored. It was concluded that installation of copper straps with molybdenum thermal radiation shields would provide the most reliable means of preventing arcing. Other design studies included torus spool electrical/structural concepts, test module shielding, torus seismic response, poloidal conditions in the magnets, disruption characteristics, and eddy current effects. These additional studies had no significant impact on cost but did confirm the feasibility of the basic FED Baseline concept

  5. 78 FR 64146 - 30-Day Notice of Proposed Information Collection: Technical Processing Requirements for...

    Science.gov (United States)

    2013-10-25

    ... Information Collection: Technical Processing Requirements for Multifamily Project Mortgage Insurance AGENCY: Office of the Chief Information Officer, HUD. ACTION: Notice. SUMMARY: HUD has submitted the proposed... Information Collection Title of Information Collection: Technical Processing Requirements for Multifamily...

  6. 78 FR 65695 - 30-Day Notice of Proposed Information Collection: Technical Processing Requirements for...

    Science.gov (United States)

    2013-11-01

    ... Information Collection: Technical Processing Requirements for Multifamily Project Mortgage Insurance AGENCY: Office of the Chief Information Officer, HUD. ACTION: Correction, notice. SUMMARY: On October 25, 2013 at... Collection Title of Information Collection: Technical Processing Requirements for Multifamily Project...

  7. Pinellas Plant Environmental Baseline Report

    Energy Technology Data Exchange (ETDEWEB)

    1997-06-01

    The Pinellas Plant has been part of the Department of Energy`s (DOE) nuclear weapons complex since the plant opened in 1957. In March 1995, the DOE sold the Pinellas Plant to the Pinellas County Industry Council (PCIC). DOE has leased back a large portion of the plant site to facilitate transition to alternate use and safe shutdown. The current mission is to achieve a safe transition of the facility from defense production and prepare the site for alternative uses as a community resource for economic development. Toward that effort, the Pinellas Plant Environmental Baseline Report (EBR) discusses the current and past environmental conditions of the plant site. Information for the EBR is obtained from plant records. Historical process and chemical usage information for each area is reviewed during area characterizations.

  8. Integrated Baseline Review (IBR) Handbook

    Science.gov (United States)

    Fleming, Jon F.; Kehrer, Kristen C.

    2016-01-01

    The purpose of this handbook is intended to be a how-to guide to prepare for, conduct, and close-out an Integrated Baseline Review (IBR). It discusses the steps that should be considered, describes roles and responsibilities, tips for tailoring the IBR based on risk, cost, and need for management insight, and provides lessons learned from past IBRs. Appendices contain example documentation typically used in connection with an IBR. Note that these appendices are examples only, and should be tailored to meet the needs of individual projects and contracts. Following the guidance in this handbook will help customers and suppliers preparing for an IBR understand the expectations of the IBR, and ensure that the IBR meets the requirements for both in-house and contract efforts.

  9. US/Japan collaborative program on fusion reactor materials: Summary of the tenth DOE/JAERI Annex I technical progress meeting on neutron irradiation effects in first wall and blanket structural materials

    International Nuclear Information System (INIS)

    Rowcliffe, A.F.

    1989-01-01

    This meeting was held at Oak Ridge National Laboratory on March 17, 1989, to review the technical progress on the collaborative DOE/JAERI program on fusion reactor materials. The purpose of the program is to determine the effects of neutron irradiation on the mechanical behavior and dimensional stability of US and Japanese austenitic stainless steels. Phase I of the program focused on the effects of high concentrations of helium on the tensile, fatigue, and swelling properties of both US and Japanese alloys. In Phase II of the program, spectral and isotropic tailoring techniques are fully utilized to reproduce the helium:dpa ratio typical of the fusion environment. The Phase II program hinges on a restart of the High Flux Isotope Reactor by mid-1989. Eight target position capsules and two RB* position capsules have been assembled. The target capsule experiments will address issues relating to the performance of austenitic steels at high damage levels including an assessment of the performance of a variety of weld materials. The RB* capsules will provide a unique and important set of data on the behavior of austenitic steels irradiated under conditions which reproduce the damage rate, dose, temperature, and helium generation rate expected in the first wall and blanket structure of the International Thermonuclear Experimental Reactor

  10. Fusion power demonstration: baseline report

    International Nuclear Information System (INIS)

    Henning, C.D.; Logan, B.G.; Neef, W.S.

    1984-01-01

    An overview is given of the FPD project. A technical discussion of the primary independent plasma parameters, the physics constraints that limited the allowed combinations of those parameters for ignition, and the basic plasma scaling laws that govern FPD plasma parameters are described. Plans are detailed for phased construction and operation of FPD. The components for FPD are based on those designed for the Mirror Advanced Reactor Study (MARS). Although FPD costs are based on the MARS first-of-a-kind estimates, FPD contains design modifications made to reduce these costs. The preliminary results of siting and safety studies are described. An essential element of FPD design is the ability to perform remote maintenance on the equipment. The key research and development issues associated with the design and implementation of an FPD facility are highlighted

  11. Underground storage tank - Integrated Demonstration Technical Task Plan master schedule

    International Nuclear Information System (INIS)

    Johnson, C.M.

    1994-08-01

    This document provides an integrated programmatic schedule (i.e., Master Schedule) for the U.S. Department of Energy (DOE) Underground Storage Tank-Integrated Demonstration (UST-ID) Program. It includes top-level schedule and related information for the DOE Office of Technology Development (EM-50) UST-ID activities. The information is based upon the fiscal year (FY) 1994 technical task plans (TTPS) and has been prepared as a baseline information resource for program participants. The Master Schedule contains Level 0 and Level 1 program schedules for the UST-ID Program. This document is one of a number of programmatic documents developed to support and manage the UST-ID activities. It is composed of the following sections: Program Overview - provides a summary background of the UST-ID Program. This summary addresses the mission, scope, and organizational structure of the program; Activity Description - provides a programmatic description of UST-ID technology development activities and lists the key milestones for the UST-ID systems. Master Schedules - contains the Level 0 and Level 1 programmatic schedules for the UST-ID systems. References - lists the UST-ID programmatic documents used as a basis for preparing the Master Schedule. The appendixes contain additional details related to site-specific technology applications

  12. Hepatitis C treatment response kinetics and impact of baseline predictors

    DEFF Research Database (Denmark)

    Lindh, M; Arnholm, B; Eilard, A

    2011-01-01

    Summary. The optimal duration of treatment for hepatitis C virus (HCV) infections is highly variable but critical for achieving cure (sustained virological response, SVR). We prospectively investigated the impact of age, fibrosis, baseline viraemia and genotype on the early viral kinetics...... above 400 000 IU/mL were strongly associated with slower second phase declines of HCV RNA. Genotype 2/3 infections responded more rapidly than genotype 1, reaching week 4 negativity (RVR) in 59%vs 22%. We conclude that baseline response predictors such as age, fibrosis and viral load were well reflected...... by the early viral kinetics as assessed by repeated HCV RNA quantifications. The kinetic patterns and the high relapse rate in genotype 2/3 patients without RVR suggest that this group might benefit from treatment durations longer than 24 weeks....

  13. Sea testing and optimisation of power production on a scale 1:4.5 test rig of the offshore wave energy converter wave dragon. Summary of final technical report

    Energy Technology Data Exchange (ETDEWEB)

    2006-06-15

    The 4-11 MW Wave Dragon is a slack moored device that can be deployed in large parks wherever a sufficient wave climate and a water depth of more than 20 m is found--typically this is the case in the North Sea and in the Atlantic, offering significant economic and environmental benefits for the EU. The primary objective of the project was to establish the scientific knowledge base needed for deploying a full-scale prototype of the overtopping wave energy converter Wave Dragon. This has been obtained through long-term field-testing on a test rig with all systems installed. The scale 1:4.5 prototype has an installed power of 20 kW corresponding to 4 MW in full-scale with full-turbine deployment and is grid connected. The scale 1:4.5 prototype has been designed based on the conclusions from a previous EU Craft project. The basic test rig construction is provided through a project sponsored by the Danish Energy Authority. The test site is in protected waters in Nissum Bredning, Denmark, where the wave climate resembles North Sea conditions (scale 1:4.5) which in accordance with model law resembles a power scale of 1:200. The test results after more than 20,000 hours of operation cover: Long-term field testing of turbine operation, control strategy testing and optimisation, power monitoring and evaluation, stress and strain measurements and analysis, and mooring and cable systems analysis. The model tools developed in the previous EU Craft project have been validated and slightly modified based on the measured data. A Life Cycle Analysis and Finite Element Modelling have been performed. A report on market analysis, economic risk assessment and job creation potential has also been carried out. The project has established the necessary scientific and technical knowledge base for engaging in the establishment of a full-scale prototype in exposed waters. This includes the existence of a well-established design basis and documentation of technical viability through long

  14. Technical Note

    African Journals Online (AJOL)

    Administratör

    In this report on four patients, we did not use any of these techniques. The existence and the site of the fistulas was clearly demonstrated using basic but important preoperative detailed assessment and two intraoperative findings. The preoperative referral note that indicated the site of technical difficulty during the previous ...

  15. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball

    2010-01-01

    Operational Experience At the end of the first full-year running period of LHC, CMS is established as a reliable, robust and mature experiment. In particular common systems and infrastructure faults accounted for <0.6 % CMS downtime during LHC pp physics. Technical operation throughout the entire year was rather smooth, the main faults requiring UXC access being sub-detector power systems and rack-cooling turbines. All such problems were corrected during scheduled technical stops, in the shadow of tunnel access needed by the LHC, or in negotiated accesses or access extensions. Nevertheless, the number of necessary accesses to the UXC averaged more than one per week and the technical stops were inevitably packed with work packages, typically 30 being executed within a few days, placing a high load on the coordination and area management teams. It is an appropriate moment for CMS Technical Coordination to thank all those in many CERN departments and in the Collaboration, who were involved in CMS techni...

  16. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball

    2010-01-01

    Operational Experience Since the closure of the detector in February, the technical operation of CMS has been quite smooth and reliable. Some minor interventions in UXC were required to cure failures of power supplies, fans, readout boards and rack cooling connections, but all these failures were repaired in scheduled technical stops or parasitically during access dedicated to fixing LHC technical problems. The only occasion when CMS had to request an access between fills was to search for the source of an alarm from the leak-detection cables mounted in the DT racks. After a few minutes of diagnostic search, a leaking air-purge was found. Replacement was complete within 2 hours. This incident demonstrated once more the value of these leak detection cables; the system will be further extended (during the end of year technical stop) to cover more racks in UXC and the floor beneath the detector. The magnet has also been operating reliably and reacted correctly to the 14s power cut on 29 May (see below). In or...

  17. Technical endoscopy

    International Nuclear Information System (INIS)

    Cavalar, K.O.

    1988-01-01

    A survey is provided on different versions of endoscopes, taking into account the new developments of video endoscopy. With a variety of practical examples it is shown that technical tests using endoscopy are a demanding task for nondestructive testing, whose requirements can only be met on a customized basis. (orig./HP) [de

  18. Technical Training: Technical Training Seminar

    CERN Multimedia

    2004-01-01

    TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch Monday 9 February 2004 From 10:00 to 12:00 - IT Auditorium - bldg. 31, 3rd floor ANSOFT High-Frequency Seminar David Prestaux, Application Engineer, ANSOFT F-78535 BUC, France This Technical Training seminar will present two Ansoft application products: Ansoft HFSS and Ansoft Designer. Ansoft HFSS makes use of the Finite Element Method (FEM) to calculate field solutions from first principles. It can accurately predict all high-frequency behaviours such as dispersion, mode conversion, and losses due to materials and radiation. Ansoft Designer is a suite of design tools to fully integrate high-frequency, physics-based electromagnetic simulations into a seamless system-level simulation environment. Ansoft Designer uses a simple interface to give complete control over every design task, by a method allowing multiple solvers, Solver on Demand. • Introduction • Overview of the Ansoft Total solution • Ansoft HFSS 9...

  19. The California Baseline Methane Survey

    Science.gov (United States)

    Duren, R. M.; Thorpe, A. K.; Hopkins, F. M.; Rafiq, T.; Bue, B. D.; Prasad, K.; Mccubbin, I.; Miller, C. E.

    2017-12-01

    The California Baseline Methane Survey is the first systematic, statewide assessment of methane point source emissions. The objectives are to reduce uncertainty in the state's methane budget and to identify emission mitigation priorities for state and local agencies, utilities and facility owners. The project combines remote sensing of large areas with airborne imaging spectroscopy and spatially resolved bottom-up data sets to detect, quantify and attribute emissions from diverse sectors including agriculture, waste management, oil and gas production and the natural gas supply chain. Phase 1 of the project surveyed nearly 180,000 individual facilities and infrastructure components across California in 2016 - achieving completeness rates ranging from 20% to 100% per emission sector at < 5 meters spatial resolution. Additionally, intensive studies of key areas and sectors were performed to assess source persistence and variability at times scales ranging from minutes to months. Phase 2 of the project continues with additional data collection in Spring and Fall 2017. We describe the survey design and measurement, modeling and analysis methods. We present initial findings regarding the spatial, temporal and sectoral distribution of methane point source emissions in California and their estimated contribution to the state's total methane budget. We provide case-studies and lessons learned about key sectors including examples where super-emitters were identified and mitigated. We summarize challenges and recommendations for future methane research, inventories and mitigation guidance within and beyond California.

  20. Hydrogeology baseline study Aurora Mine

    International Nuclear Information System (INIS)

    1996-01-01

    A baseline hydrogeologic study was conducted in the area of Syncrude's proposed Aurora Mine in order to develop a conceptual regional hydrogeologic model for the area that could be used to understand groundwater flow conditions. Geologic information was obtained from over 2,000 coreholes and from data obtained between 1980 and 1996 regarding water level for the basal aquifer. A 3-D numerical groundwater flow model was developed to provide quantitative estimates of the potential environmental impacts of the proposed mining operations on the groundwater flow system. The information was presented in the context of a regional study area which encompassed much of the Athabasca Oil Sands Region, and a local study area which was defined by the lowlands of the Muskeg River Basin. Characteristics of the topography, hydrology, climate, geology, and hydrogeology of the region are described. The conclusion is that groundwater flow in the aquifer occurs mostly in a westerly direction beneath the Aurora Mine towards its inferred discharge location along the Athabasca River. Baseflow in the Muskeg River is mostly related to discharge from shallow surficial aquifers. Water in the river under baseflow conditions was fresh, of calcium-carbonate type, with very little indication of mineralization associated with deeper groundwater in the Aurora Mine area. 44 refs., 5 tabs., 31 figs

  1. 2016 Annual Technology Baseline (ATB)

    Energy Technology Data Exchange (ETDEWEB)

    Cole, Wesley; Kurup, Parthiv; Hand, Maureen; Feldman, David; Sigrin, Benjamin; Lantz, Eric; Stehly, Tyler; Augustine, Chad; Turchi, Craig; O' Connor, Patrick; Waldoch, Connor

    2016-09-01

    Consistent cost and performance data for various electricity generation technologies can be difficult to find and may change frequently for certain technologies. With the Annual Technology Baseline (ATB), National Renewable Energy Laboratory provides an organized and centralized dataset that was reviewed by internal and external experts. It uses the best information from the Department of Energy laboratory's renewable energy analysts and Energy Information Administration information for conventional technologies. The ATB will be updated annually in order to provide an up-to-date repository of current and future cost and performance data. Going forward, we plan to revise and refine the values using best available information. The ATB includes both a presentation with notes (PDF) and an associated Excel Workbook. The ATB includes the following electricity generation technologies: land-based wind; offshore wind; utility-scale solar PV; concentrating solar power; geothermal power; hydropower plants (upgrades to existing facilities, powering non-powered dams, and new stream-reach development); conventional coal; coal with carbon capture and sequestration; integrated gasification combined cycle coal; natural gas combustion turbines; natural gas combined cycle; conventional biopower. Nuclear laboratory's renewable energy analysts and Energy Information Administration information for conventional technologies. The ATB will be updated annually in order to provide an up-to-date repository of current and future cost and performance data. Going forward, we plan to revise and refine the values using best available information.

  2. 77 FR 32712 - Technical Report: Evaluation of the Enhancing Vehicle-to-Vehicle Crash Compatibility Agreement...

    Science.gov (United States)

    2012-06-01

    ...-0070] Technical Report: Evaluation of the Enhancing Vehicle-to-Vehicle Crash Compatibility Agreement... comments on technical report. SUMMARY: This notice announces NHTSA's publication of a Technical Report... be received no later than October 1, 2012. ADDRESSES: Report: The technical report is available on...

  3. Technical and legal application possibilities of the compulsory labelling of the standby consumption of electrical household and office appliances - Project No. 53/03. Summary of the final report for the Federal Ministry of Economics and Labour

    Energy Technology Data Exchange (ETDEWEB)

    Schlomann, B.; Cremer, C.; Friedewald, M. [Fraunhofer-Institut fuer Systemtechnik und Innovationsforschung, Karlsruhe (DE)] (and others)

    2005-06-13

    The standby consumption of electrical households and office appliances continues to be significant world-wide since the number of products with standby components is constantly increasing. For Germany, a recent assessment of the Fraunhofer ISI (Cremer et al. 2003) for 2001 arrived at an electricity demand of almost 15 TWh for household and office appliances in standby mode. i.e. in standby and off-mode. This represents almost 40% of the total consumption of these appliances and around 3% of the total electricity demand of the final energy sectors in Germany. The standby share in electricity demand is over 80 or even 90% for numerous appliances. The Federal Environmental Agency calculated that every year standby losses in German households and offices are responsible for wasted electricity amounting to 3.5 billion Euro (UBA 2004). For the OECD countries, field studies show that between 3 and 13% of the electricity consumption of households can be ascribed to standby losses (IEA 2001). Without energy policy measures on both national and international levels, there is a great risk that a further increase in standby consumption will occur. Many studies dealing with this subject have already been conducted and have shown that low standby consumption is technically feasible and usually achievable at a reasonable cost. One possible energy policy measure to reduce the standby consumption of electrical household and office appliances is the introduction of mandatory consumption labelling. In principle, a high degree of effectiveness is attributed to such regulatory/command-and-control measures with regard to influencing the energy efficiency of devices. Compulsory energy labels to identify and, where necessary, to classify electricity consumption produce greater market transparency and offer buyers an additional decision criterion. In this way they promote indirectly the development, production and supply of energy-efficient products. When combined with comparatively low

  4. Minutes of the IFMIF technical meeting

    International Nuclear Information System (INIS)

    Nakamura, H.; Takeda, M.; Ida, M.; Maebara, S.; Yutani, T.; Sugimoto, M.

    2004-03-01

    The IFMIF Technical Meeting was held on December 4-5, 2003 at Shiran-kaikan, Kyoto University. The main objectives are 1) to finalize the Comprehensive Design Report (CDR), 2) to discuss IFMIF cost and organization, 3) to review technical status of major systems, transition phase activities and EVEDA plan. This report presents a brief summary of the results of the meeting. Agenda, participants list and presentation materials are attached as Appendix. (author)

  5. Summary of Research 1998, Department of Physics

    OpenAIRE

    Faculty of the Department of Physics, Naval Postgraduate School

    1998-01-01

    The views expressed in this report are those of the authors and do not reflect the official policy or position of the Department of Defense or the U.S. Government. This report contains summaries of research projects in the Department of Physics. A list of recent publications is also included which consists of conference presentations and publications, books, contributions to books, published journal papers, technical reports, and thesis abstracts.

  6. Nuclear Energy Innovation Workshops. Executive Summary

    Energy Technology Data Exchange (ETDEWEB)

    Allen, Todd [Idaho National Lab. (INL), Idaho Falls, ID (United States); Jackson, John [Idaho National Lab. (INL), Idaho Falls, ID (United States); Hildebrandt, Phil [Idaho National Lab. (INL), Idaho Falls, ID (United States); Baker, Suzy [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-06-01

    The nuclear energy innovation workshops were organized and conducted by INL on March 2-4, 2015 at the five NUC universities and Boise State University. The output from these workshops is summarized with particular attention to final summaries that were provided by technical leads at each of the workshops. The current revision includes 3-4 punctuation corrections and a correction of the month of release from May to June.

  7. ITER technical basis

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-01-01

    Following on from the Final Report of the EDA(DS/21), and the summary of the ITER Final Design report(DS/22), the technical basis gives further details of the design of ITER. It is in two parts. The first, the Plant Design specification, summarises the main constraints on the plant design and operation from the viewpoint of engineering and physics assumptions, compliance with safety regulations, and siting requirements and assumptions. The second, the Plant Description Document, describes the physics performance and engineering characteristics of the plant design, illustrates the potential operational consequences foe the locality of a generic site, gives the construction, commissioning, exploitation and decommissioning schedule, and reports the estimated lifetime costing based on data from the industry of the EDA parties.

  8. ITER technical basis

    International Nuclear Information System (INIS)

    2002-01-01

    Following on from the Final Report of the EDA(DS/21), and the summary of the ITER Final Design report(DS/22), the technical basis gives further details of the design of ITER. It is in two parts. The first, the Plant Design specification, summarises the main constraints on the plant design and operation from the viewpoint of engineering and physics assumptions, compliance with safety regulations, and siting requirements and assumptions. The second, the Plant Description Document, describes the physics performance and engineering characteristics of the plant design, illustrates the potential operational consequences foe the locality of a generic site, gives the construction, commissioning, exploitation and decommissioning schedule, and reports the estimated lifetime costing based on data from the industry of the EDA parties

  9. 2016 Annual Technology Baseline (ATB) - Webinar Presentation

    Energy Technology Data Exchange (ETDEWEB)

    Cole, Wesley; Kurup, Parthiv; Hand, Maureen; Feldman, David; Sigrin, Benjamin; Lantz, Eric; Stehly, Tyler; Augustine, Chad; Turchi, Craig; Porro, Gian; O' Connor, Patrick; Waldoch, Connor

    2016-09-13

    This deck was presented for the 2016 Annual Technology Baseline Webinar. The presentation describes the Annual Technology Baseline, which is a compilation of current and future cost and performance data for electricity generation technologies.

  10. 75 FR 66748 - Notice of Baseline Filings

    Science.gov (United States)

    2010-10-29

    ...- 000] Notice of Baseline Filings October 22, 2010. ONEOK Gas Transportation, L.L.C Docket No. PR11-68... above submitted a revised baseline filing of their Statement of Operating Conditions for services...

  11. FEMA Disaster Declarations Summary

    Data.gov (United States)

    Department of Homeland Security — The FEMA Disaster Declarations Summary is a summarized dataset describing all federally declared disasters, starting with the first disaster declaration in 1953,...

  12. Program Baseline Change Control Board charter

    International Nuclear Information System (INIS)

    1993-02-01

    The purpose of this Charter is to establish the Program Baseline Change Control Board (PBCCB) for the Office of Civilian Radioactive Waste Management (OCRWM) Program, and to describe its organization, responsibilities, and basic methods of operation. Guidance for implementing this Charter is provided by the OCRWM Baseline Management Plan (BMP) and OCRWM Program Baseline Change Control Procedure

  13. 40 CFR 1042.825 - Baseline determination.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 32 2010-07-01 2010-07-01 false Baseline determination. 1042.825... Provisions for Remanufactured Marine Engines § 1042.825 Baseline determination. (a) For the purpose of this... not valid. (f) Use good engineering judgment for all aspects of the baseline determination. We may...

  14. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball

    Overview From a technical perspective, CMS has been in “beam operation” state since 6th November. The detector is fully closed with all components operational and the magnetic field is normally at the nominal 3.8T. The UXC cavern is normally closed with the radiation veto set. Access to UXC is now only possible during downtimes of LHC. Such accesses must be carefully planned, documented and carried out in agreement with CMS Technical Coordination, Experimental Area Management, LHC programme coordination and the CCC. Material flow in and out of UXC is now strictly controlled. Access to USC remains possible at any time, although, for safety reasons, it is necessary to register with the shift crew in the control room before going down.It is obligatory for all material leaving UXC to pass through the underground buffer zone for RP scanning, database entry and appropriate labeling for traceability. Technical coordination (notably Stephane Bally and Christoph Schaefer), the shift crew and run ...

  15. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball and W. Zeuner

    2011-01-01

    In this report we will review the main achievements of the Technical Stop and the progress of several centrally-managed projects to support CMS operation and maintenance and prepare the way for upgrades. Overview of the extended Technical Stop  The principal objectives of the extended Technical Stop affecting the detector itself were the installation of the TOTEM T1 telescopes on both ends, the readjustment of the alignment link-disk in YE-2, the replacement of the light-guide sleeves for all PMs of both HFs, and some repairs on TOTEM T2 and CASTOR. The most significant tasks were, however, concentrated on the supporting infrastructure. A detailed line-by-line leak search was performed in the C6F14 cooling system of the Tracker, followed by the installation of variable-frequency drives on the pump motors of the SS1 and SS2 tracker cooling plants to reduce pressure transients during start-up. In the electrical system, larger harmonic filters were installed in ...

  16. SCOPING SUMMARY FOR THE P-AREA OPERABLE UNIT

    International Nuclear Information System (INIS)

    Kupar, J; Sadika Baladi, S; Mark Amidon, M

    2007-01-01

    This scoping summary supports development of the combined Remedial Investigation (RI)/Baseline Risk Assessment (BRA)/Feasibility Study (FS) for the P-Area Operable Unit (PAOU), or Combined document, which will be submitted on or before 09/28/2007. The objective of this Feasibility Study scoping summary meeting is to agree on the likely response actions to be evaluated and developed as alternatives in the combined document and agree on the uncertainties identified and whether they have been adequately managed

  17. SCOPING SUMMARY FOR THE P-AREA OPERABLE UNIT

    Energy Technology Data Exchange (ETDEWEB)

    Kupar, J; Sadika Baladi, S; Mark Amidon, M

    2007-05-22

    This scoping summary supports development of the combined Remedial Investigation (RI)/Baseline Risk Assessment (BRA)/Feasibility Study (FS) for the P-Area Operable Unit (PAOU), or Combined document, which will be submitted on or before 09/28/2007. The objective of this Feasibility Study scoping summary meeting is to agree on the likely response actions to be evaluated and developed as alternatives in the combined document and agree on the uncertainties identified and whether they have been adequately managed.

  18. Summary information report

    International Nuclear Information System (INIS)

    1982-07-01

    The Summary Information Report (SIR) provides summary data concerning NRC and its licensees for general use by the Chairman, other Commissioners and Commission staff offices, the Executive Director for Operations, and the Office Directors. SIR is published quarterly by the Management Information Branch (49-27834) of the Office of Resource Management

  19. Plutonium focus area. Technology summary

    International Nuclear Information System (INIS)

    1997-09-01

    The Assistant Secretary for the Office of Environmental Management (EM) at the U.S. Department of Energy (DOE) chartered the Plutonium Focus Area (PFA) in October 1995. The PFA open-quotes...provides for peer and technical reviews of research and development in plutonium stabilization activities...close quotes In addition, the PFA identifies and develops relevant research and technology. The purpose of this document is to focus attention on the requirements used to develop research and technology for stabilization, storage, and preparation for disposition of nuclear materials. The PFA Technology Summary presents the approach the PFA uses to identify, recommend, and review research. It lists research requirements, research being conducted, and gaps where research is needed. It also summarizes research performed by the PFA in the traditional research summary format. This document encourages researchers and commercial enterprises to do business with PFA by submitting research proposals or open-quotes white papers.close quotes In addition, it suggests ways to increase the likelihood that PFA will recommend proposed research to the Nuclear Materials Stabilization Task Group (NMSTG) of DOE

  20. Plutonium focus area: Technology summary

    International Nuclear Information System (INIS)

    1996-03-01

    To ensure research and development programs focus on the most pressing environmental restoration and waste management problems at the U.S. Department of Energy (DOE), the Assistant Secretary for the Office of Environmental Management (EM) established a working group in August 1993 to implement a new approach to research and technology development. As part of this approach, EM developed a management structure and principles that led to creation of specific focus areas. These organizations were designed to focus scientific and technical talent throughout DOE and the national scientific community on major environmental restoration and waste management problems facing DOE. The focus area approach provides the framework for inter-site cooperation and leveraging of resources on common problems. After the original establishment of five major focus areas within the Office of Technology Development (EM-50), the Nuclear Materials Stabilization Task Group (NMSTG, EM-66) followed EM-50's structure and chartered the Plutonium Focus Area (PFA). NMSTG's charter to the PFA, described in detail later in this book, plays a major role in meeting the EM-66 commitments to the Defense Nuclear Facilities Safety Board (DNFSB). The PFA is a new program for FY96 and as such, the primary focus of revision 0 of this Technology Summary is an introduction to the Focus Area; its history, development, and management structure, including summaries of selected technologies being developed. Revision 1 to the Plutonium Focus Area Technology Summary is slated to include details on all technologies being developed, and is currently planned for release in August 1996. The following report outlines the scope and mission of the Office of Environmental Management, EM-60, and EM-66 organizations as related to the PFA organizational structure

  1. Integrated Baseline System (IBS) Version 2.0: Models guide

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    The Integrated Baseline System (IBS) is an emergency management planning and analysis tool being developed under the direction of the US Army Nuclear and Chemical Agency. This Models Guide summarizes the IBS use of several computer models for predicting the results of emergency situations. These include models for predicting dispersion/doses of airborne contaminants, traffic evacuation, explosion effects, heat radiation from a fire, and siren sound transmission. The guide references additional technical documentation on the models when such documentation is available from other sources. The audience for this manual is chiefly emergency management planners and analysts, but also data managers and system managers.

  2. Continuum of eLearning: 2012 Project Summary Report

    Science.gov (United States)

    2012-10-01

    multimedia, and Continuum of eLearning | Purpose and Vision 19 << UNCLASSIFIED>> (limited) situated learning. Future versions of the CoL self-paced...Continuum of eLearning : 2012 Project Summary Report Continuum of eLearning The Next Evolution of Joint Training on JKO October 2012 Joint...Technical Report November 2011 – August 2012 Continuum of eLearning : 2012 Project Summary Report N00140-06-D-0060 David T. Fautua, Sae Schatz, Andrea

  3. Livermore Big Trees Park: 1998 summary results; TOPICAL

    International Nuclear Information System (INIS)

    Gallegos, G; MacQueen, D; Surano, K

    1999-01-01

    This report summarizes work conducted in 1998 by the Lawrence Livermore National Laboratory (LLNL) to determine the extent and origin of plutonium at concentrations above background levels at Big Trees Park in the city of Livermore. This summary includes the project background and sections that explain the sampling, radiochemical and data analysis, and data interpretation. This report is a summary report only and is not intended as a rigorous technical or statistical analysis of the data

  4. Corrective action baseline report for underground storage tank 2331-U Building 9201-1

    International Nuclear Information System (INIS)

    1994-01-01

    The purpose of this report is to provide baseline geochemical and hydrogeologic data relative to corrective action for underground storage tank (UST) 2331-U at the Building 9201-1 Site. Progress in support of the Building 9201-1 Site has included monitoring well installation and baseline groundwater sampling and analysis. This document represents the baseline report for corrective action at the Building 9201-1 site and is organized into three sections. Section 1 presents introductory information relative to the site, including the regulatory initiative, site description, and progress to date. Section 2 includes the summary of additional monitoring well installation activities and the results of baseline groundwater sampling. Section 3 presents the baseline hydrogeology and planned zone of influence for groundwater remediation

  5. Technical and Management Information System (TMIS)

    Science.gov (United States)

    Rau, Timothy R.

    1987-01-01

    The TMIS goals developed to support the Space Station Program (SSP) mission requirements are outlined. The TMIS will provide common capabilities to all SSP centers and facilitate the flow of technical and management information throughout the program as well as SSP decision-making processes. A summary is presented of the various TMIS phases.

  6. Technical Training: Technical Training Seminar

    CERN Multimedia

    2004-01-01

    Tuesday 30 March TECHNICAL TRAINING SEMINAR From 9:00 to 12:00 and from 13:00 to 16:00 hrs - Council Chamber, Salle B, Salle des Pas Perdus National Instruments (NI) on Tour 2004 Claudia Jüngel, Evrem Yarkin, Joel Clerc, Hervé Baour / NATIONAL INSTRUMENTS The special event NI on Tour 2004, run in Germany, Austria and Switzerland, will be at CERN on March 30. Technical seminars and free introductory courses will be offered all day long in the Council Chamber, Salle B, and Salle des Pas Perdus (buildings 61 and 503). Technical conferences: 09:00 - 12:00 Data acquisition systems on PCs. Industrial measurement and control techniques. 13:00 - 16:00 Advanced LabVIEW software and PXI instrumentation. Measuring instruments and system components for teststand automation. Introductory courses: 09:00 - 12:00 DIAdem: Data analysis and presentation 13:00 - 16:00 Data acquisition with LabVIEW Language: English and French Free special seminar. Registration is recommended with National Instruments Switzerland (please sp...

  7. Technical Training: Technical Training Seminar

    CERN Multimedia

    2004-01-01

    Tuesday 30 March TECHNICAL TRAINING SEMINAR From 9:00 to 12:00 and from 13:00 to 16:00 hrs - Council Chamber, Salle B, Salle des Pas Perdus National Instruments (NI) on Tour 2004 Claudia Jüngel, Evrem Yarkin, Joel Clerc, Hervé Baour / NATIONAL INSTRUMENTS The special event NI on Tour 2004, run in Germany, Austria and Switzerland, will be at CERN on March 30. Technical seminars and free introductory courses will be offered all day long in the Council Chamber, Salle B, and Salle des Pas Perdus (buildings 61 and 503). Technical conferences: 09:00 - 12:00 Data acquisition systems on PCs. Industrial measurement and control techniques. 13:00 - 16:00 Advanced LabVIEW software and PXI instrumentation. Measuring instruments and system components for teststand automation. Introductory courses: 09:00 - 12:00 DIAdem: Data analysis and presentation 13:00 - 16:00 Data acquisition with LabVIEW Language: English and French Free special seminar. Registration is recommended with National Instruments Swi...

  8. Office of Civilian Radioactive Waste Management Program Cost and Schedule Baseline

    International Nuclear Information System (INIS)

    1992-09-01

    The purpose of this document is to establish quantitative expressions of proposed costs and schedule to serve as a basis for measurement of program performance. It identifies the components of the Program Cost and Schedule Baseline (PCSB) that will be subject to change control by the Executive (Level 0) and Program (Level 1) Change Control Boards (CCBS) and establishes their baseline values. This document also details PCSB reporting, monitoring, and corrective action requirements. The Program technical baseline contained in the Waste Management System Description (WMSD), the Waste Management System Requirements (WMSR), and the Physical System Requirements documents provide the technical basis for the PCSB. Changes to the PCSB will be approved by the Pregrain Change Control Board (PCCB)In addition to the PCCB, the Energy System Acquisition Advisory Board Baseline CCB (ESAAB BCCB) will perform control functions relating to Total Project Cost (TPC) and major schedule milestones for the Yucca Mountain Site Characterization Project and the Monitored Retrievable Storage (MRS) Project

  9. Research and Technology Objectives and Plans Summary (RTOPS)

    Science.gov (United States)

    1993-01-01

    This publication represents the NASA research and technology program for FY-93. It is a compilation of the Summary portions of each of the RTOP's (Research and Technology Objectives and Plans) used for management review and control of research currently in progress throughout NASA. The RTOP Summary is designed to facilitate communication and coordination among concerned technical personnel in government, in industry, and in universities. The first section containing citations and abstracts of the RTOP's is followed by four indexes: Subject, Technical Monitor, Responsible NASA Organization, and RTOP Number.

  10. 40 CFR 74.20 - Data for baseline and alternative baseline.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 16 2010-07-01 2010-07-01 false Data for baseline and alternative baseline. 74.20 Section 74.20 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR... baseline and alternative baseline. (a) Acceptable data. (1) The designated representative of a combustion...

  11. Baseline radiological monitoring at proposed uranium prospecting site at Rohil Sikar, Rajasthan

    International Nuclear Information System (INIS)

    Kumar, Rajesh; Jha, V.N.; Sahoo, N.K.; Jha, S.K.; Tripathi, R.M.

    2018-01-01

    Once economically viable grades of uranium deposits are proposed for mining and processing by the industry radiological baseline studies are required for future comparison during operational phases. The information collected during such studies serve as connecting feature between regulatory compliance and technical information. Present paper summarizes the results of baseline monitoring of atmospheric 222 Rn and gamma level in the area at prospecting mining, milling and waste disposal sites of Rohil Rajasthan

  12. TECHNICAL COORDINATION

    CERN Document Server

    A. Ball and W. Zeuner

    2013-01-01

    For the reporting period, the CMS common systems and infrastructure worked well, without failures that caused significant data losses. One more disconnection of the magnet cold box occurred in the shadow of interruptions in data taking, caused by a series of technical faults. The recognition during 2012 that re-connection can only safely be done at around 2 T implies a minimum magnet recovery time of 12 hours and raises serious concerns about the number of ramping cycles of the magnet these incidents cause. This has triggered studies of how to make the cryo-system of the magnet more robust against failures. The proton-proton run ended just before the end-of-year CERN closure, during which CASTOR was installed on the negative end of CMS and both ZDC calorimeters were installed in TAN absorbers the LHC tunnel, in preparation for the heavy-ion run. The installation of CASTOR was an excellent “engineering test” of procedures for working in an activated environment. Despite some technical pr...

  13. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball and W. Zeuner

    2011-01-01

      Operational experience 2011 CMS is approaching the end of a very successful year of operation. Proton- proton running ended in the late afternoon of 30th October with a stunning 5.73 fb–1 delivered by LHC, of which CMS recorded 5.22 fb–1. During heavy-ion operation, which continues until 7th December, both the accelerator and the CMS detector have also performed very well. Despite the encouraging overall reliability of technical operation, several infrastructure failures which occurred since the last Bulletin are worthy of mention, with one leading for the first time to significant data-loss. On 10th July, a CERN-wide power failure brought down essentially all services including the magnet, due to an MCS setting being left in “manual” after the recent technical stop, but there was no significant damage and the detector was operational before the LHC, despite a slow and tortuous recovery (one of several indications this year that there is room for improve...

  14. 77 FR 50488 - Hydrogen and Fuel Cell Technical Advisory Committee

    Science.gov (United States)

    2012-08-21

    ... DEPARTMENT OF ENERGY Hydrogen and Fuel Cell Technical Advisory Committee AGENCY: Department of...). SUMMARY: This notice announces an open meeting (Webinar) of the Hydrogen and Fuel Cell Technical Advisory... Avenue, Washington, DC 20585. SUPPLEMENTARY INFORMATION: Purpose of the Committee: The Hydrogen and Fuel...

  15. The Agency's technical co-operation activities in 1993

    International Nuclear Information System (INIS)

    1994-08-01

    This document reviews the IAEA's Technical Cooperation activities for 1993. Apart from an overview, the report contains reviews by Agency programmes and technical divisions, by area, by component and by fund. Summaries of project implementation are also included, as well as indications of the achievements of projects completed in 1993

  16. Summary big data

    CERN Document Server

    2014-01-01

    This work offers a summary of Cukier the book: "Big Data: A Revolution That Will Transform How we Live, Work, and Think" by Viktor Mayer-Schonberg and Kenneth. Summary of the ideas in Viktor Mayer-Schonberg's and Kenneth Cukier's book: " Big Data " explains that big data is where we use huge quantities of data to make better predictions based on the fact we identify patters in the data rather than trying to understand the underlying causes in more detail. This summary highlights that big data will be a source of new economic value and innovation in the future. Moreover, it shows that it will

  17. Biofuels: Project summaries

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    The US DOE, through the Biofuels Systems Division (BSD) is addressing the issues surrounding US vulnerability to petroleum supply. The BSD goal is to develop technologies that are competitive with fossil fuels, in both cost and environmental performance, by the end of the decade. This document contains summaries of ongoing research sponsored by the DOE BSD. A summary sheet is presented for each project funded or in existence during FY 1993. Each summary sheet contains and account of project funding, objectives, accomplishments and current status, and significant publications.

  18. Safety evaluation of the ESP sludge washing baselines runs. Revision 2

    International Nuclear Information System (INIS)

    Gupta, M.K.

    1993-01-01

    Purpose is to provide the technical basis for evaluation of unreviewed safety question for the Extended Sludge Processing (ESP) Sludge Washing Baseline Runs, which are necessary to resolve technical questions associated with process control (sludge suspension, sludge settling, heat transfer, temperature control). The sludge is currently stored in below-ground tanks and will be prepared for processing at the Defense Waste Processing Facility as part of the Integrated Waste Removal Program for Savannah River Site

  19. Summaries of FY 1989 research in the chemical sciences

    International Nuclear Information System (INIS)

    1989-08-01

    These summaries provide the scientific and technical public, as well as the legislative and executive branches of the Government, information, either generally or in some depth, about the Chemical Sciences program. Areas of research supported are indicated in the section headings, the ''Selected Topics of General Interest'' list, and the summaries themselves. Energy technologies that may be advanced by use of the basic knowledge generated in this program are included in the ''Selected Topics of General Interest'' list and are often referenced in the summaries

  20. Hazard Baseline Downgrade Effluent Treatment Facility

    International Nuclear Information System (INIS)

    Blanchard, A.

    1998-01-01

    This Hazard Baseline Downgrade reviews the Effluent Treatment Facility, in accordance with Department of Energy Order 5480.23, WSRC11Q Facility Safety Document Manual, DOE-STD-1027-92, and DOE-EM-STD-5502-94. It provides a baseline grouping based on the chemical and radiological hazards associated with the facility. The Determination of the baseline grouping for ETF will aid in establishing the appropriate set of standards for the facility

  1. RAMP 2003 summary report

    International Nuclear Information System (INIS)

    Moats, D.; Stanley, S.; Abundo, L.; Theriault, C.; Bruce, G.; Gibbons, W.

    2003-01-01

    This report summarized key findings of the 2003 Regional Aquatics Monitoring Program (RAMP) annual technical report. RAMP was formed in 1997 to monitor the health of rivers and lakes in the oil sands region of Alberta and to assess the potential impacts of oil sands development. It was also developed to collect baseline data and compare it with environmental assessment predictions made by oil sand operators in the Wood Buffalo region. In 2003, RAMP monitored fish and fish habitats in the oil sands region, as well as water and sediment quality. Data was also collected on benthic invertebrates; wetlands vegetation; lake acidification data; hydrology; and climate. Studies focused on the Athabasca River and its tributaries; smaller tributaries of the Muskeg River; the North Steepbank River; and the Christina River. Data from wetlands in the vicinity of current and proposed oil sands developments was collected together with data from 50 acid-sensitive lakes in northeastern Alberta. RAMP monitoring activities in 2003 increased in response to increased resource exploitation activities in the region. Information from climate and hydrologic monitoring stations was analyzed in order to model changes resulting from oil sands development. Water levels were monitored to measure discharge, ice thickness, and water depth of selected lakes and streams. Water and sediment quality analyses were conducted to establish the physical and chemical features of the water bodies in the RAMP study area. The analyses suggested that water quality was consistent with previous years. Inputs from tributaries in the oil sands region did not obviously impact water quality in the Athabasca River. Higher levels of polycyclic aromatic hydrocarbons (PAHs) were noted at stations in the oil sands regions. Benthic communities monitored in the study were within expected ranges for undisturbed communities in the region. A RAMP fish monitoring program indicated that spawning runs in the Muskeg River have

  2. IPCC Socio-Economic Baseline Dataset

    Data.gov (United States)

    National Aeronautics and Space Administration — The Intergovernmental Panel on Climate Change (IPCC) Socio-Economic Baseline Dataset consists of population, human development, economic, water resources, land...

  3. Worldwide Airfield Summary

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Worldwide Airfield Summary contains a selection of climatological data produced by the U.S. Air Force, Air Weather Service. The reports were compiled from dozens...

  4. Annual Meteorological Summaries

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Single-year summaries of observations at Weather Bureau and cooperative stations across the United States. Predominantly the single page Form 1066, which includes...

  5. Global Climate Summaries

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Global Hourly Summaries are simple indicators of observational normals which include climatic data summarizations and frequency distributions. These typically...

  6. Cancer Information Summaries

    Science.gov (United States)

    Peer-reviewed, evidence-based summaries on topics including adult and pediatric cancer treatment, supportive and palliative care, screening, prevention, genetics, and complementary and alternative medicine. References to published literature are included.

  7. Summaries of poster contributions

    International Nuclear Information System (INIS)

    1981-01-01

    The 10. meeting covered subjects on the application of electron microscopy in numerous fields such as biology and medicine, solid state physics, semiconductor research and production, crystallography, materials science, and chemistry of polymers. 174 summaries of poster contributions are included

  8. Oceanographic Monthly Summary

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Oceanographic Monthly Summary contains sea surface temperature (SST) analyses on both regional and ocean basin scales for the Atlantic, Pacific, and Indian Oceans....

  9. MSIS State Summary Datamarts

    Data.gov (United States)

    U.S. Department of Health & Human Services — This page provides background needed to take advantage of the capabilities of the MSIS State Summary Datamart. This mart allows the user to develop high-level...

  10. Summary status of K Basins sludge characterization

    International Nuclear Information System (INIS)

    Baker, R.B.

    1995-01-01

    A number of activities are underway as part of the Spent Nuclear Fuels Project (SNFP) related to the processing and disposing of sludge in the 105-K Basins (K Basins). Efforts to rigorously define data requirements for these activities are being made using the Data Quality Objectives (DQO) process. Summaries of current sludge characterization data are required to both help support this DQO process and to allow continued progress with on-going engineering activities (e.g., evaluations of disposal alternatives). This document provides the status of K Basins sludge characterization data currently available to the Nuclear Fuel Evaluations group. This group is tasked by the SNFP to help develop and maintain the characterization baseline for the K Basins. The specific objectives of this document are to: (1) provide a current summary (and set of references) of sludge characterization data for use by SNFP initiatives, to avoid unnecessary duplication of effort and to support on-going initiatives; (2) submit these data to an open forum for review and comment, and identify additional sources of significant data that may be available; (3) provide a summary of current data to use as part of the basis to develop requirements for additional sludge characterization data through the DQO process; (4) provide an overview of the intended activities that will be used to develop and maintain the sludge characterization baseline

  11. Technical presentation

    CERN Multimedia

    GS Department

    2010-01-01

    10 March 2010 DYNEOS 10:00 – 12:00 - Main Building, Room B, 61-1-009 Dyneos AG is active in the fields of photonics, laser and high-precision positioning. Our highly qualified engineer team has more than 30 years of experience in electro-optical solutions sales. The engineers are supported by a technical and administrative team. We are focused on the Swiss market and represent six suppliers (Coherent, PI Physik Instrumente, SIOS, Nanonics Imaging, APE, Ekspla) in order to give a qualified sales and service support to our customers. Our products are dedicated to the research field as well as to industry. In addition to standard catalog products, we offer custom designs to fulfill the specific needs of OEM customers or specific applications.

  12. Technical presentation

    CERN Document Server

    FP Department

    2009-01-01

    07 April 2009 Technical presentation by Leuze Electronics: 14.00 – 15.00, Main Building, Room 61-1-017 (Room A) Photoelectric sensors, data identification and transmission systems, image processing systems. We at Leuze Electronics are "the sensor people": we have been specialising in optoelectronic sensors and safety technology for accident prevention for over 40 years. Our dedicated staff are all highly customer oriented. Customers of Leuze Electronics can always rely on one thing – on us! •\tFounded in 1963 •\t740 employees •\t115 MEUR turnover •\t20 subsidiaries •\t3 production facilities in southern Germany Product groups: •\tPhotoelectric sensors •\tIdentification and measurements •\tSafety devices

  13. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball and W. Zeuner

    2010-01-01

    Overview Once again, the bulk of this article reviews the intense activity of a recently completed shutdown, which, although quite unforeseeable until a few weeks before it started, proved by its success that our often advertised capability to conduct major maintenance within a two month period is real. Although safely completed, on-time to remarkable precision, the activity was not without incident, and highlighted our dependence on many experienced, specialist teams and their precise choreography. Even after the yoke was safely closed, magnet re-commissioning and beampipe pumpdown showed new and thought-provoking behaviour. The struggle to maintain adequate technical resources will be a pre-occupation over the coming months, in parallel with the start of truly sustained operation, for which various procedures are still being put in place. Planning for future shutdowns must now become a high priority, with many working groups and task forces already in existence to prepare infrastructure improvements and to...

  14. Technical presentation

    CERN Document Server

    FI Department

    2008-01-01

    RADIOSPARES, the leading catalogue distributor of components (electronic, electrical, automation, etc.) and industrial supplies will be at CERN on Friday 3 October 2008 (Main Building, Room B, from 9.00 a.m. to 3.00 p.m.) to introduce its new 2008/2009 catalogue. This will be the opportunity for us to present our complete range of products in more detail: 400 000 part numbers available on our web site (Radiospares France, RS International, extended range of components from other manufacturers); our new services: quotations, search for products not included in the catalogue, SBP products (Small Batch Production: packaging in quantities adapted to customers’ requirements); partnership with our focus manufacturers; demonstration of the on-line purchasing tool implemented on our web site in conjunction with CERN. RADIOSPARES will be accompanied by representatives of FLUKE and TYCO ELECTRONICS, who will make presentations, demonstrate materials and answer any technical questio...

  15. Summary of blog

    CERN Document Server

    Reader, Capitol

    2013-01-01

    This ebook consists of a summary of the ideas, viewpoints and facts presented by Hugh Hewitt in his book "Blog: Understanding the Information Reformation that's Changing Your World". This summary offers a concise overview of the entire book in less than 30 minutes reading time. However this work does not replace in any case Hugh Hewitt's book.Hewitt argues that blogs have an important potential and he believes that it would be a dreadful mistake to avoid their power.

  16. Site environmental report summary

    International Nuclear Information System (INIS)

    1992-01-01

    In this summary of the Fernald 1992 Site Environmental Report the authors will describe the impact of the Fernald site on man and the environment and provide results from the ongoing Environmental Monitoring Program. Also included is a summary of the data obtained from sampling conducted to determine if the site complies with DOE, US Environmental Protection Agency (USEPA), and Ohio EPA (OEPA) requirements. These requirements are set to protect both man and the environment

  17. Technical Training: Technical Training Seminar

    CERN Multimedia

    2004-01-01

    TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch Tuesday 3 February 2004 From 09:00 to 13:30 - Training Centre Auditorium - bldg. 593, room 11 USB (Universal Serial Bus) CYPRESS Seminar Claudia Colombini, Field Application Engineer CYPRESS ActiveComp Electronic GmbH D-85077 MANCHING, Germany As a pioneer in USB, CYPRESS sets the standard for cost-effective solutions without sacrificing functionality, performance or reliability. Having shipped over 200 million USB devices, Cypress is the undisputed market leader and demonstrates unmatched USB expertise. With the industry's broadest selection of USB solutions, Cypress has the right silicon, software and support for every USB application, from Low-speed to High-Speed and USB On-The-Go (OTG). 9:00 - 10:30 Overview of USB systems. USB CYPRESS product overview. Peripherals: Low Speed, Full Speed, High Speed (1.1 and 2.0). Hub Solutions, Embedded Host Solutions, On-The-Go (OTG) and wireless USB. USB Development Tools (first part) 10:30 -...

  18. Distributed Mission Operations Within-Simulator Training Effectiveness Baseline Study. Volume 5. Using the Pathfinder Methodology to Assess Pilot Knowledge Structure Changes

    National Research Council Canada - National Science Library

    Schreiber, Brian T; DiSalvo, Pam; Stock, William A; Bennett, Jr., Winston

    2006-01-01

    ...) Within Simulator Training Effectiveness Baseline Study as described in Volume I, Summary Report, of AFRL-HE-AZ-TR-2006-0015, the current work examined pilots who participated in a Pathfinder data...

  19. TAPIR--Finnish national geochemical baseline database.

    Science.gov (United States)

    Jarva, Jaana; Tarvainen, Timo; Reinikainen, Jussi; Eklund, Mikael

    2010-09-15

    In Finland, a Government Decree on the Assessment of Soil Contamination and Remediation Needs has generated a need for reliable and readily accessible data on geochemical baseline concentrations in Finnish soils. According to the Decree, baseline concentrations, referring both to the natural geological background concentrations and the diffuse anthropogenic input of substances, shall be taken into account in the soil contamination assessment process. This baseline information is provided in a national geochemical baseline database, TAPIR, that is publicly available via the Internet. Geochemical provinces with elevated baseline concentrations were delineated to provide regional geochemical baseline values. The nationwide geochemical datasets were used to divide Finland into geochemical provinces. Several metals (Co, Cr, Cu, Ni, V, and Zn) showed anomalous concentrations in seven regions that were defined as metal provinces. Arsenic did not follow a similar distribution to any other elements, and four arsenic provinces were separately determined. Nationwide geochemical datasets were not available for some other important elements such as Cd and Pb. Although these elements are included in the TAPIR system, their distribution does not necessarily follow the ones pre-defined for metal and arsenic provinces. Regional geochemical baseline values, presented as upper limit of geochemical variation within the region, can be used as trigger values to assess potential soil contamination. Baseline values have also been used to determine upper and lower guideline values that must be taken into account as a tool in basic risk assessment. If regional geochemical baseline values are available, the national guideline values prescribed in the Decree based on ecological risks can be modified accordingly. The national geochemical baseline database provides scientifically sound, easily accessible and generally accepted information on the baseline values, and it can be used in various

  20. Air Force Office of Scientific Research. AFOSR Technical Report Summaries

    Science.gov (United States)

    1993-06-01

    0..’ w z CA W B mL& L53 )I-t in (3w - J 2.5 W 1I- C12 z. WJO -1 )-. U’.aW 64 1--2 0 .Z 9 0 F- ... w ’.LILOO 4z w W’ IL =Aw M 4%0 J.IZW w . u zw -jO...x &-~ a 4 5 i ɜ (A W CDI- #_ z U r) (j 𔃺 ’- )_ *𔃾 We. a:U IA. aL U 014 U ’A -2 m 0 0 I--U’ o n (A z- w ý4 0 #- $.- U’>- tD I.- z 40 I-. a: x 4z- 0Z...toMM CC 0In L~A001 L - - oc -n C’ -- n x C4 L W - M A ’- 0 l. -A LO C SLS 0&c 0 0 0 0. 0+ a14 SI 41 > -a:I 0 c 1X’ .0 m z tD a1 -_ 1 U 8-01 --. 81 00 C

  1. Evaluation of Motorcycle Safety in Kansas : Technical Summary

    Science.gov (United States)

    2012-01-01

    Over the past several years, motorcycle fatalities have increased at an alarming rate in the United States. Motorcycle safety issues in Kansas are no different from the national scenario. Accordingly, this study attempted to investigate motorcycle cr...

  2. Workshop on technical assessment of industrial thermal insulation materials: summary

    International Nuclear Information System (INIS)

    Peterson, S.

    1976-07-01

    Over 80 participants representing 50 organizations met to discuss the report, Industrial Thermal Insulation--An Assessment, ORNL/TM-5283. Presentations on the performance of available materials, economic considerations, and measurement problems were followed by discussion. A final wrap-up session concluded that the report was valuable in pointing the direction for needed effort in the area, confirmed the indicated actions needed to further industrial application of insulation, and called for future meetings to continue the dialogue between the various facets of the industry

  3. Long-term behavior of integral abutment bridges : [technical summary].

    Science.gov (United States)

    2011-01-01

    Integral abutment bridges, a type of jointless bridge, are the construction option of choice when designing highway bridges in many parts of the country. Rather than providing an expansion joint to separate the substructure from the superstructure to...

  4. Characterizing soil erosion potential using electrical resistivity imaging : technical summary.

    Science.gov (United States)

    2017-04-01

    The erosion rate, or erodibility, of soil depends on many soil characteristics : including: plasticity, water content, grain size, percent clay, compaction, and shear : strength. Many of these characteristics also influence soil in situ bulk electric...

  5. Lime Kiln Dust for Treated Subgrades : Technical Summary

    Science.gov (United States)

    2017-11-01

    Chemical and cementitious materials are often used to modify and stabilize the subgrade soils that serve as foundations for pavements. Improvement of the subgrade provides a better working platform for construction of the layers above and improves th...

  6. AFOSR (Air Force Office of Scientific Research) Technical Report Summaries

    Science.gov (United States)

    1988-10-01

    4’ 4’C W4’ u ... U -uC .4)- ’.L> I L - 1 CA A 123 oe . p. LUJ O D.D qr 0’ ’A ’.4 1,o *0 ~ & L40 t%~ 0L’ 420 cc ~4 F6 - LI_- A OX 0 e 04 w 140" OL Lo...3IU0o w a - L 0.- ’a UU 0 0M 0* -A C 00 0 a . 0 0 to UL w I >. 2W; F!. c o=I U Do ;60 acCa -0 U. U * W 0* o-4 LA-4 0L c W’ - Cla a aS -CU W - -o 0 - Iu...U C 40.f *0 0- 4cI at-0 >4. 1-PcA C C SI9 0 ;I. r- -- S 3D 6-6 0L 4.I. a~ 16 I 4w X* L:: IL VI5 AC0. 0 0q0- -a ow L F6 * 4 c6!o -L -IOS01-4 EIi

  7. Accommodating oversize/overweight vehicles at roundabouts : [technical summary].

    Science.gov (United States)

    2013-02-01

    Safety and traffic operational benefits of roundabouts for the typical vehicle fleet (automobiles and small trucks) have been well documented. Although roundabouts have been in widespread use in other countries for many years, their general use in th...

  8. Performance evaluation of traffic sensing and control devices : [technical summary].

    Science.gov (United States)

    2011-01-01

    High quality sensing and control systems are essential for providing efficient signalized arterial operations. INDOT operates over 2600 traffic signal controllers, approximately 2000 of which use some form of vehicle detection. The private sector con...

  9. Technical committee meeting on fuel and cladding interaction. Summary report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-04-01

    Experiments and experiences concerning fuel-cladding interaction in thermal and fast neutron flux burnup are dealt with. A number of results from in-pile and out-of pile experiments with different fuel pins with cladding made of different stainless steels showed the importance of corrosion process, dependent on the burnup, core temperature, metal-oxide ratio, and other steady state parameters in the core of fast reactors (most frequently LMFBRs). This is of importance for fuel pins design and fabrication. Mixed oxide fuel is treated in many cases.

  10. Potential well formation in electrostatic confinement devices. Technical summary report

    International Nuclear Information System (INIS)

    Cherrington, B.E.; Verdeyen, J.T.

    1978-01-01

    The experimental and theoretical studies on Inertial Electrostatic Plasma Confinement that have been performed in the Gaseous Electronics Laboratory of the University of Illinois are reviewed. There has been experimental confirmation of the production of a multiple potential structure in both small and large spherical devices and the theoretical analysis has indicated the parameter range that is necessary in order to explain such results. Further experimental and theoretical approaches to testing the IEPC concept are suggested

  11. Identification and behavior of collapsible soils : [technical summary].

    Science.gov (United States)

    2011-01-01

    Collapsible soils are susceptible to large volumetric strains when they become saturated. Numerous soil types : fall in the general category of collapsible soils, including : loess, a well-known aeolian deposit, present throughout : most of Indiana. ...

  12. Louisiana CVO/ITS business plan : technical summary.

    Science.gov (United States)

    1998-06-01

    Louisiana seeks to improve the efficiency and effectiveness of CVO business and operational functions in the state. This overall mission includes three discrete elements designed to address priority needs as identified by state and industry stakehold...

  13. Subsurface Contamination Focus Area technical requirements. Volume 1: Requirements summary

    International Nuclear Information System (INIS)

    Nickelson, D.; Nonte, J.; Richardson, J.

    1996-10-01

    This document summarizes functions and requirements for remediation of source term and plume sites identified by the Subsurface Contamination Focus Area. Included are detailed requirements and supporting information for source term and plume containment, stabilization, retrieval, and selective retrieval remedial activities. This information will be useful both to the decision-makers within the Subsurface Contamination Focus Area (SCFA) and to the technology providers who are developing and demonstrating technologies and systems. Requirements are often expressed as graphs or charts, which reflect the site-specific nature of the functions that must be performed. Many of the tradeoff studies associated with cost savings are identified in the text

  14. Technical committee meeting on fuel and cladding interaction. Summary report

    International Nuclear Information System (INIS)

    1977-04-01

    Experiments and experiences concerning fuel-cladding interaction in thermal and fast neutron flux burnup are dealt with. A number of results from in-pile and out-of pile experiments with different fuel pins with cladding made of different stainless steels showed the importance of corrosion process, dependent on the burnup, core temperature, metal-oxide ratio, and other steady state parameters in the core of fast reactors (most frequently LMFBRs). This is of importance for fuel pins design and fabrication. Mixed oxide fuel is treated in many cases

  15. Technical summaries of Scotian Shelf - significant and commercial discoveries

    International Nuclear Information System (INIS)

    Dickey, J.E.; Bigelow, S.F.; Edens, J.A.; Brown, D.E.; Smith, B.; Makrides, C.; Mader, R.

    1997-03-01

    An independent assessment of the recoverable hydrocarbon resource currently held under' Significant and Commercial Discovery' status offshore Nova Scotia was presented. A generalized description of the regulatory issues regarding the discovered resources within the Scotian Basin was included. Twenty discoveries have been declared significant and two have been declared commercial, pursuant to the Canada-Nova Scotia Offshore Petroleum Resources Accord Implementation Acts. Salient facts about each discovery were documented. The information included the wells drilled within the structure, significant flow tests, geological and geophysical attributes, structural cross-section and areal extent, petrophysical parameters, hydrocarbons in place and anticipated hydrocarbon recoverable resource. tabs., figs

  16. AFOSR Technical Report Summaries, April-June 1986,

    Science.gov (United States)

    1986-06-01

    216 Ordered Ionic Layers Formed on ’ EDITING Pt(11ll from Aqueous Solutions. The Engineering of an ’ELECTRIC CHARGE AD-A167 i70 Environment on Small...Robust Signal Processing. *EFTIS, J. Superconducting Accelerometer and AD-AI66 147 * * * Gravity Gradlometer. Life Prediction for a Structural AD- AISA ...polygonal obstacles. By applying standard DESCRIPTORS: (U] ’ EDITING , SYNTAX, TRADE OFF ANALYSIS. Plgorithms for point location, we can determine the

  17. A model study of bridge hydraulics : technical summary.

    Science.gov (United States)

    2010-08-01

    Most flood studies in the United States use the Army Corps of Engineers Hydrologic Engineering Centers River Analysis System (HEC-RAS) computer program. This report is the second edition. The first edition of the report considered the laboratory m...

  18. Technical information program summary: radiation protection - issues, terms, definitions

    International Nuclear Information System (INIS)

    1979-01-01

    Questions concerning the health effects and risks of exposure to ionizing radiations are presented and answered on a popular level. Definitions are given for various working terms. A defense is made of the radiation protection policies of Westinghouse Hanford Company

  19. Analysis of INDOT current hydraulic policies : [technical summary].

    Science.gov (United States)

    2011-01-01

    Hydraulic design often tends to be on a conservative side for safety reasons. Hydraulic structures are typically oversized with the goal being reduced future maintenance costs, and to reduce the risk of property owner complaints. This approach leads ...

  20. Prep-ME Software Implementation and Enhancement : technical summary

    Science.gov (United States)

    2017-09-01

    Pavement ME Design (previously MEPDG/DARWin-ME) is a significant advancement in pavement design, though requiring more inputs from various sources. Through efforts by the Louisiana Transportation Research Center (LTRC) and Federal Highway Administrat...