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Sample records for technical review meeting

  1. Proceedings of the 24th NSRR technical review meeting

    Energy Technology Data Exchange (ETDEWEB)

    Uetsuka, Hiroshi; Fuketa, Toyoshi; Suzuki, Motoe [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

    2001-09-01

    The 24th NSRR Technical Review Meeting was held at Tranomon Pastoral, Tokyo, on November 13 and 14, 2000. The purpose of the meeting was to present and discuss the recent progress of the NSRR program and other LWR fuel safety researches at JAERI. Twenty-one papers, including five by foreign institutes, were presented and discussed regarding fuel behavior during normal operation, reactivity initiated accident (RIA) and loss-of-coolant accident (LOCA) and FP release behavior during severe accident. The meeting was a great help in planning future research and promoting research cooperation. This proceeding contains the papers presented in the meeting. (author)

  2. 76 FR 17970 - Board Meeting: April 27, 2011-Amherst, New York; the U.S. Nuclear Waste Technical Review Board...

    Science.gov (United States)

    2011-03-31

    ... NUCLEAR WASTE TECHNICAL REVIEW BOARD Board Meeting: April 27, 2011--Amherst, New York; the U.S. Nuclear Waste Technical Review Board Will Meet To Discuss the West Valley Demonstration Project Pursuant to its authority under section 5051 of Public Law 100-203, Nuclear Waste Policy Amendments Act of...

  3. Advanced Mixed Waste Treatment Project melter system preliminary design technical review meeting

    International Nuclear Information System (INIS)

    Eddy, T.L.; Raivo, B.D.; Soelberg, N.R.; Wiersholm, O.

    1995-02-01

    The Idaho National Engineering Laboratory Advanced Mixed Waste Treatment Project sponsored a plasma are melter technical design review meeting to evaluate high-temperature melter system configurations for processing heterogeneous alpha-contaminated low-level radioactive waste (ALLW). Thermal processing experts representing Department of Energy contractors, the Environmental Protection Agency, and private sector companies participated in the review. The participants discussed issues and evaluated alternative configurations for three areas of the melter system design: plasma torch melters and graphite arc melters, offgas treatment options, and overall system configuration considerations. The Technical Advisory Committee for the review concluded that graphite arc melters are preferred over plasma torch melters for processing ALLW. Initiating involvement of stakeholders was considered essential at this stage of the design. For the offgas treatment system, the advisory committee raised the question whether to a use wet-dry or a dry-wet system. The committee recommended that the waste stream characterization, feed preparation, and the control system are essential design tasks for the high-temperature melter treatment system. The participants strongly recommended that a complete melter treatment system be assembled to conduct tests with nonradioactive surrogate waste material. A nonradioactive test bed would allow for inexpensive design and operational changes prior to assembling a system for radioactive waste treatment operations

  4. Advanced Mixed Waste Treatment Project melter system preliminary design technical review meeting

    Energy Technology Data Exchange (ETDEWEB)

    Eddy, T.L.; Raivo, B.D.; Soelberg, N.R.; Wiersholm, O.

    1995-02-01

    The Idaho National Engineering Laboratory Advanced Mixed Waste Treatment Project sponsored a plasma are melter technical design review meeting to evaluate high-temperature melter system configurations for processing heterogeneous alpha-contaminated low-level radioactive waste (ALLW). Thermal processing experts representing Department of Energy contractors, the Environmental Protection Agency, and private sector companies participated in the review. The participants discussed issues and evaluated alternative configurations for three areas of the melter system design: plasma torch melters and graphite arc melters, offgas treatment options, and overall system configuration considerations. The Technical Advisory Committee for the review concluded that graphite arc melters are preferred over plasma torch melters for processing ALLW. Initiating involvement of stakeholders was considered essential at this stage of the design. For the offgas treatment system, the advisory committee raised the question whether to a use wet-dry or a dry-wet system. The committee recommended that the waste stream characterization, feed preparation, and the control system are essential design tasks for the high-temperature melter treatment system. The participants strongly recommended that a complete melter treatment system be assembled to conduct tests with nonradioactive surrogate waste material. A nonradioactive test bed would allow for inexpensive design and operational changes prior to assembling a system for radioactive waste treatment operations.

  5. Review of design approaches of advanced pressurized LWRs. Report of a technical committee meeting and workshop

    International Nuclear Information System (INIS)

    1996-01-01

    The Technical Committee Meeting and Workshop was devoted to review and discuss differences and commonalties in the various design approaches with the aim of increasing the understanding of the design decisions taken, and a number of general conclusions were drawn. Though many differences in design approaches were found in the presentations, a number of common features could also be identified. These included design approaches to achieve further improvements with respect to safety, design simplification, reduction in cost, incorporation of feedback from operating experience, and control room improvements regarding human factors and digitization. Design approaches to achieve further improvements in safety included consideration of severe accidents in the design process, increased thermal margins and water inventories, longer grace periods and double containments. Refs, figs and tabs

  6. Boiling eXperiment Facility (BXF) Fluid Toxicity Technical Interchange Meeting (TIM) with the Payload Safety Review Panel (PSRP)

    Science.gov (United States)

    Sheredy, William A.

    2012-01-01

    A Technical Interchange meeting was held between the payload developers for the Boiling eXperiment Facility (BXF) and the NASA Safety Review Panel concerning operational anomaly that resulted in overheating one of the fluid heaters, shorted a 24VDC power supply and generated Perfluoroisobutylene (PFiB) from Perfluorohexane.

  7. Technical meeting to 'Review of national programmes on fast reactors and accelerator driven systems (ADS)'. Working material

    International Nuclear Information System (INIS)

    2002-01-01

    The 35th Annual Meeting of the Technical Working Group on Fast Reactors TWG-FR, previously International Working Group on Fast Reactors (IWG-FR, created in 1967), was hosted by the Forschungszentrum Karlsruhe (FZK) and was attended by TWG-FR members and advisers from the following Member States: Brazil, China, France, Germany, India, Japan, the Republic of Kazakhstan, the Republic of Korea, the Russian Federation, and the United States of America. The objectives of the meeting were: to exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); to review the progress since the 34th TWG-FR Annual Meeting, including the status of the actions; to consider meeting arrangements for 2002 and 2003; to review the Agency's co-ordinated research activities in the field of FRs and ADS, as well as co-ordination of the TWG-FR's activities with other organizations

  8. 77 FR 60430 - Meeting of the Mobile Sources Technical Review Subcommittee

    Science.gov (United States)

    2012-10-03

    ... Advisory Committee Act, Public Law 92- 463, notice is hereby given that the Mobile Sources Technical Review... at The Madison Hotel at 1177 15th St. NW., Washington, DC 20005. However, this date and location are... logistical information. The hotel is located five blocks from the McPherson Square Metro Station. FOR FURTHER...

  9. 75 FR 16461 - Meeting of the Mobile Sources Technical Review Subcommittee

    Science.gov (United States)

    2010-04-01

    ... Committee Act, Public Law 92- 463, notice is hereby given that the Mobile Sources Technical Review... Hotel Crystal City-National Airport, 300 Army Navy Drive, Arlington, VA 22202-2891. Phone 703-416-4100. The hotel is located three blocks from the Pentagon City Metro station, and shuttle buses are...

  10. 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)

  11. Technical meeting (TM) to 'Review of national programmes on fast reactors and accelerator driven systems (ADS)'. Technical Working Group on Fast Reactors (TWG-FR) (37th annual meeting). Working material

    International Nuclear Information System (INIS)

    2004-01-01

    The objectives of the 37th Annual Meeting of the Technical Working Group on Fast Reactors, were to: 1) exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); 2) review the progress since the 36th TWG-FR Annual Meeting, including the status of the actions; 3) consider meeting arrangements for 2004 and 2005; 4) review the Agency's co-ordinated research activities in the field of FRs and ADS, as well as co-ordination of the TWG-FR's activities with other organizations. The participants made presentations on the status of the respective national programmes on FR and ADS development. A summary of the highlights for the period since the 36th TWG-FR Annual Meeting is included in this proceedings. Annex IV contains the Review of National Programs on Fast Reactors and Accelerator Driven Systems (ADS), and the TWG-FR Activity Report for the Period May 2003-April 2004

  12. 78 FR 77673 - Notification of a Public Meeting of the Environmental Justice Technical Guidance Review Panel

    Science.gov (United States)

    2013-12-24

    ...: Notice. SUMMARY: The EPA Science Advisory Board (SAB) Staff Office announces a public meeting of the SAB...:00 a.m. to 5:00 p.m. (Eastern Time). ADDRESSES: The public meeting will be held at The Renaissance..., Deputy Director, EPA Science Advisory Board Staff Office. [FR Doc. 2013-30708 Filed 12-23-13; 8:45 am...

  13. IAEA technical committee meeting on fusion safety

    International Nuclear Information System (INIS)

    Dolan, T.

    2000-01-01

    The 7th IAEA Technical Committee Meeting on Fusion Reactor Safety was held in Cannes, France on 13-16 June 2000. The purpose of the meeting was to learn lessons from current installations and studies for the future

  14. Independent technical review, handbook

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    Purpose Provide an independent engineering review of the major projects being funded by the Department of Energy, Office of Environmental Restoration and Waste Management. The independent engineering review will address questions of whether the engineering practice is sufficiently developed to a point where a major project can be executed without significant technical problems. The independent review will focus on questions related to: (1) Adequacy of development of the technical base of understanding; (2) Status of development and availability of technology among the various alternatives; (3) Status and availability of the industrial infrastructure to support project design, equipment fabrication, facility construction, and process and program/project operation; (4) Adequacy of the design effort to provide a sound foundation to support execution of project; (5) Ability of the organization to fully integrate the system, and direct, manage, and control the execution of a complex major project.

  15. Independent technical review, handbook

    International Nuclear Information System (INIS)

    1994-02-01

    Purpose Provide an independent engineering review of the major projects being funded by the Department of Energy, Office of Environmental Restoration and Waste Management. The independent engineering review will address questions of whether the engineering practice is sufficiently developed to a point where a major project can be executed without significant technical problems. The independent review will focus on questions related to: (1) Adequacy of development of the technical base of understanding; (2) Status of development and availability of technology among the various alternatives; (3) Status and availability of the industrial infrastructure to support project design, equipment fabrication, facility construction, and process and program/project operation; (4) Adequacy of the design effort to provide a sound foundation to support execution of project; (5) Ability of the organization to fully integrate the system, and direct, manage, and control the execution of a complex major project

  16. Sixth ITER technical meeting on safety and environment

    International Nuclear Information System (INIS)

    Saji, G.; Baker, D.

    1997-01-01

    The article summarizes the topics of the Sixth Technical Meeting on Safety and Environment which was held to review the first draft of the Non-Site Specific Safety Report (NSSR-2) and the draft of the ITER Final Design Report Safety Assessment (FDR-Safety) during October 27 - November 4, 1997 at the ITER San Diego Joint Work Site

  17. 76 FR 3678 - Board Meeting: February 16, 2011-Las Vegas, NV, the U.S. Nuclear Waste Technical Review Board...

    Science.gov (United States)

    2011-01-20

    ... Fuel and High-Level Radioactive Waste Pursuant to its authority under section 5051 of Public Law 100... of rooms has been reserved at the hotel for meeting attendees. To ensure receiving the meeting rate, reservations must be made by January 21, 2011. To make reservations, go to http://www.marriott.com/hotels...

  18. 77 FR 8926 - Board Meeting: March 7, 2012-Albuquerque, NM; The U.S. Nuclear Waste Technical Review Board Will...

    Science.gov (United States)

    2012-02-15

    ... Repository Geologies Pursuant to its authority under section 5051 of Public Law 100-203, the Nuclear Waste... Sheraton Albuquerque Airport Hotel, 2910 Yale Blvd. SE., Albuquerque, New Mexico 87106; (Tel) 505-843-7000; (Fax) 505-843-6307. A block of rooms has been reserved at the hotel for meeting attendees. To ensure...

  19. Eighth ITER technical meeting on safety and environment

    International Nuclear Information System (INIS)

    Gordon, C.; Raeder, J.

    2000-01-01

    From November 27 to 30, 2000 the Eighth ITER Technical Meeting on Safety and Environment was held by the ITER Joint Central Team (JCT) at the Garching Joint Work Site, which also hosts the ITER Safety, Environment and Health Group (SEHG). At this meeting, safety experts from the Home Teams (HT) worked together with the SEHG members towards the following main objectives: review of Generic Site Safety Report (GSSR) results and drafts; review of the Plant Design Description (PDD) summary of safety; update on the status of the R and D tasks contributing to GSSR

  20. Review of Meeting Objectives

    International Nuclear Information System (INIS)

    Braams, B.J.; Chung, H.-K.

    2011-01-01

    This is the 21st meeting of the International Atomic and Molecular Data Centres Network. The traditional DCN meeting objectives are: to exchange information about activities in the Centres and review progress; to coordinate work in the Centres; to assess priorities in data evaluation and data production; to make plans for specific evaluations; and to evaluate and revise procedures for collection and exchange of bibliographical and numerical data. All of these are objectives for the present meeting too. In addition to the presentations from DCN and prospective DCN members we have two participants from outside the field of fusion data: Dr N. Mason will tell us about coordination of the Virtual Atomic and Molecular Data Centre and Dr S. Simakov will describe the manner in which nuclear structure and cross-section database development is coordinated by our colleagues in the Nuclear Data Section. In the discussions on Thursday and Friday there are two topics that need special attention this year: the future of our bibliographical data compilation and ways in which we can strengthen data evaluation activities, all with emphasis on collision processes and plasma-material interaction. The first 3 Data Centre Network meetings were held in 1977, 1980 and 1982 and the reports of those meetings make interesting reading and can still provide inspiration for the present meeting. I show some excerpts in the presentation. In 1977 the emphasis was on the coordination of the bibliographical database, AMBDAS, and a collision data index, CIAMDA, as the initial activities of the Network and of the newly formed IAEA A+M Data Unit. In 1980 the central topic of discussion at the meeting shifted to the numerical database and to data evaluation. The Network recommended that numerical data be reviewed by a selected group of scientists and that no unevaluated numerical A+M collision data should be distributed by the IAEA. The report of the meeting in 1982 shows that the bibliographical

  1. DOE-DARPA High-Performance Corrosion-Resistant Materials (HPCRM), Annual HPCRM Team Meeting & Technical Review

    Energy Technology Data Exchange (ETDEWEB)

    Farmer, J; Brown, B; Bayles, B; Lemieux, T; Choi, J; Ajdelsztajn, L; Dannenberg, J; Lavernia, E; Schoenung, J; Branagan, D; Blue, C; Peter, B; Beardsley, B; Graeve, O; Aprigliano, L; Yang, N; Perepezko, J; Hildal, K; Kaufman, L; Lewandowski, J; Perepezko, J; Hildal, K; Kaufman, L; Lewandowski, J; Boudreau, J

    2007-09-21

    The overall goal is to develop high-performance corrosion-resistant iron-based amorphous-metal coatings for prolonged trouble-free use in very aggressive environments: seawater & hot geothermal brines. The specific technical objectives are: (1) Synthesize Fe-based amorphous-metal coating with corrosion resistance comparable/superior to Ni-based Alloy C-22; (2) Establish processing parameter windows for applying and controlling coating attributes (porosity, density, bonding); (3) Assess possible cost savings through substitution of Fe-based material for more expensive Ni-based Alloy C-22; (4) Demonstrate practical fabrication processes; (5) Produce quality materials and data with complete traceability for nuclear applications; and (6) Develop, validate and calibrate computational models to enable life prediction and process design.

  2. Engineering Technical Review Planning Briefing

    Science.gov (United States)

    Gardner, Terrie

    2012-01-01

    The general topics covered in the engineering technical planning briefing are 1) overviews of NASA, Marshall Space Flight Center (MSFC), and Engineering, 2) the NASA Systems Engineering(SE) Engine and its implementation , 3) the NASA Project Life Cycle, 4) MSFC Technical Management Branch Services in relation to the SE Engine and the Project Life Cycle , 5) Technical Reviews, 6) NASA Human Factor Design Guidance , and 7) the MSFC Human Factors Team. The engineering technical review portion of the presentation is the primary focus of the overall presentation and will address the definition of a design review, execution guidance, the essential stages of a technical review, and the overall review planning life cycle. Examples of a technical review plan content, review approaches, review schedules, and the review process will be provided and discussed. The human factors portion of the presentation will focus on the NASA guidance for human factors. Human factors definition, categories, design guidance, and human factor specialist roles will be addressed. In addition, the NASA Systems Engineering Engine description, definition, and application will be reviewed as background leading into the NASA Project Life Cycle Overview and technical review planning discussion.

  3. Proceedings of the first technical committee meeting held in Vienna, Austria, 17-20 November 1987

    International Nuclear Information System (INIS)

    1987-01-01

    This was the first Technical Committee meeting organized by the International Atomic Energy Agency on reactivity transient accidents as a response to recommendations made during the Chernobyl Post Accident Review Meeting (25-29 August 1986) and the subsequent Member States Experts meeting to review the IAEA expanded nuclear safety programme. The Technical Committee meeting was attended by 46 representatives from 28 countries and 1 international organization. The objectives of the Technical Committee meeting were: to review the state of knowledge and to assess the remaining safety questions relating to reactivity initiated accidents (RIAs); to share experience and information on RIA assessment and relevant fuel experiments; to formulate conclusions on what the consensus might be on safety aspects of the RIAs; and to provide recommendations for sharing the technical information and for IAEA assistance to Member States. A separate abstract was prepared for each of the 17 presentations of this meeting. Refs, figs and tabs

  4. Mechanical Engineering Department Technical Review

    Energy Technology Data Exchange (ETDEWEB)

    Carr, R.B.; Denney, R.M. (eds.)

    1981-07-01

    The Mechanical Engineering Department Technical Review is published to inform readers of various technical activities within the Department, promote exchange of ideas, and give credit to personnel who are achieving the results. The report is presented in two parts: technical achievements and publication abstracts. The first is divided into seven sections, each of which reports on an engineering division and its specific activities related to nuclear tests, nuclear explosives, weapons, energy systems, engineering sciences, magnetic fusion, and materials fabrication.

  5. Mechanical engineering department technical review

    International Nuclear Information System (INIS)

    Carr, R.B.; Denney, R.M.

    1981-01-01

    The Mechanical Engineering Department Technical Review is published to: (1) inform the readers of various technical activities within the department, (2) promote exchange of ideas, and (3) give credit to the personnel who are achieving the results. The report is formatted into two parts: technical acievements and publication abstracts. The first is divided into eight sections, one for each division in the department providing the reader with the names of the personnel and the division accomplishing the work

  6. Mechanical Engineering Department. Technical review

    Energy Technology Data Exchange (ETDEWEB)

    Simecka, W.B.; Condouris, R.A.; Talaber, C. (eds.)

    1980-01-01

    The Mechanical Engineering Department Technical Review is published to (1) inform the readers of various technical activities within the Department, (2) promote exchange of ideas, and (3) give credit to the personnel who are achieving the results. The report is formatted into two parts: technical achievements and publication abstracts. The first is divided into eight sections, one for each Division in the Department providing the reader with the names of the personnel and the Division accomplishing the work.

  7. Mechanical engineering department technical review

    Energy Technology Data Exchange (ETDEWEB)

    Carr, R.B. Denney, R.M. (eds.)

    1981-01-01

    The Mechanical Engineering Department Technical Review is published to: (1) inform the readers of various technical activities within the department, (2) promote exchange of ideas, and (3) give credit to the personnel who are achieving the results. The report is formatted into two parts: technical acievements and publication abstracts. The first is divided into eight sections, one for each division in the department providing the reader with the names of the personnel and the division accomplishing the work.

  8. Mechanical Engineering Department. Technical review

    International Nuclear Information System (INIS)

    Simecka, W.B.; Condouris, R.A.; Talaber, C.

    1980-01-01

    The Mechanical Engineering Department Technical Review is published to (1) inform the readers of various technical activities within the Department, (2) promote exchange of ideas, and (3) give credit to the personnel who are achieving the results. The report is formatted into two parts: technical achievements and publication abstracts. The first is divided into eight sections, one for each Division in the Department providing the reader with the names of the personnel and the Division accomplishing the work

  9. Mechanical Engineering Department Technical Review

    International Nuclear Information System (INIS)

    Carr, R.B.; Denney, R.M.

    1981-01-01

    The Mechanical Engineering Department Technical Review is published to inform readers of various technical activities within the Department, promote exchange of ideas, and give credit to personnel who are achieving the results. The report is presented in two parts: technical achievements and publication abstracts. The first is divided into seven sections, each of which reports on an engineering division and its specific activities related to nuclear tests, nuclear explosives, weapons, energy systems, engineering sciences, magnetic fusion, and materials fabrication

  10. 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…

  11. Review of technical specifications

    International Nuclear Information System (INIS)

    Bedrich, M.; Scholz, D.

    1980-01-01

    The present paper deals with position and function of technical specifications before and during the manufacturing of reactor components, their structure and reasons for specific regulations due to safety philosophy and explains the cooperation of supplier, manufacturer, utilities and supervisory organizations. (RW)

  12. 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)

  13. 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).

  14. 76 FR 29333 - Pipeline Safety: Meetings of the Technical Pipeline Safety Standards Committee and the Technical...

    Science.gov (United States)

    2011-05-20

    ... pipeline rehabilitation, replacement and repair initiatives along with all forum-related comments. PHMSA... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Meetings of the Technical Pipeline Safety Standards Committee and the Technical Hazardous Liquid Pipeline Safety Standards Committee AGENCY...

  15. Mechanical Engineering Department technical review

    Energy Technology Data Exchange (ETDEWEB)

    Carr, R.B.; Abrahamson, L.; Denney, R.M.; Dubois, B.E (eds.)

    1982-01-01

    Technical achievements and publication abstracts related to research in the following Divisions of Lawrence Livermore Laboratory are reported in this biannual review: Nuclear Fuel Engineering; Nuclear Explosives Engineering; Weapons Engineering; Energy Systems Engineering; Engineering Sciences; Magnetic Fusion Engineering; and Material Fabrication. (LCL)

  16. IAEA International Database on Irradiated Nuclear Graphite Properties. 6th meeting of the Technical Steering Committee

    International Nuclear Information System (INIS)

    Humbert, D.; Wickham, A.J.

    2004-12-01

    This report summarizes the Consultant Meeting 6th Meeting of the Technical Steering Committee for the International Database on Irradiated Nuclear Graphite Properties' held on 16-17 September 2004 at Plas Tan-Y-Bwlch, Maentwrog, Gwynedd, UK. 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 to make recommendations for actions for the next year. The purposes of the meeting were fully met. This report contains the current status of the identified actions as well as a summary of the recommendations on enhancements to the database. (author)

  17. IAEA International Database on Irradiated Nuclear Graphite Properties. 7th meeting of the Technical Steering Committee

    International Nuclear Information System (INIS)

    Humbert, D.; Wickham, A.J.

    2005-06-01

    This report summarizes the Consultant Meeting '7th Meeting of the Technical Steering Committee for the International Database on Irradiated Nuclear Graphite Properties' held on 16-17 March 2005 at the IAEA Headquarters, Vienna, Austria. 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 to make recommendations for actions for the next year. The purposes of the meeting were fully met. This report contains the current status of the identified actions as well as a summary of the recommendations on enhancements to the database. (author)

  18. Technical meeting on materials for in-vessel components of ITER

    International Nuclear Information System (INIS)

    Kalinin, G.; Barabash, V.

    2000-01-01

    The Technical meeting on materials for in-vessel components of ITER was held at the ITER Joint Work Site in Garching from 31 January to 4 February. The main objectives of the meetings were: 1. to summarize the requirements, 2. to review new data, 3. to discuss in detail the R and D program and to discuss the material assessment report

  19. Development and field evaluation of animal feed supplementation packages. Proceedings of the final review meeting of an IAEA Technical Co-operation Regional AFRA Project

    International Nuclear Information System (INIS)

    2002-06-01

    evaluate reproductive performance in animals that are subjected to different feed supplementation strategies. It was, however, realised that this technique has potential to monitor and improve existing support services to livestock farmers such as artificial insemination and to introduce new services such as early diagnosis of non-pregnancy and infertility. In order to ensure future sustainability of the RIA for use in such applications, the work on the second component has now been taken under a new project (RAF/5/046). This publication contains the results presented by the scientists of National Agricultural Research Systems of African countries who participated in the Final Review meeting held in Cairo, Egypt from 25 to 29 November 2000, which dealt with only the nutrition component, Development and Field Evaluation of Feed Supplementation Strategies. This publication also contains some selected papers presented at the National Training Workshop on Field Evaluation and Development of the Dry Season Feed Supplementation Packages for Ruminant Animals in the Traditional Smallholder Farms organized with financial assistance from the IAEA, from 25 to 29 July 1999, in Lusaka, Zambia

  20. Proceedings of the Efficient Separations and Processing Cross-Cutting Program Annual Technical Exchange Meeting

    International Nuclear Information System (INIS)

    1995-01-01

    This document contains summaries of technology development presented at the 1995 Efficient Separations and Processing Cross-Cutting Program (ESP) Annual Technical Exchange Meeting. The ESP is sponsored by the US Department of Energy's Office of Environmental Management (EM), Office of Technology Development. The meeting is held annually to promote a free exchange of ideas among technology developers, potential users (for example, EM focus areas), and other interested parties within EM. During this meeting, developers of ESP-funded technologies describe the problems and needs addressed by their technologies; the technical approach, accomplishments, and resolution of issues; the strategy and schedule for commercialization; and evolving potential applications. Presenters are asked to address the following areas: Target waste management problem, waste stream, or data need; scientific background and technical approach; technical accomplishments and resolution of technical issues; schedule and strategy for commercializing and implementing the technology or acquiring needed data; potential alternate applications of the technology or data, including outside of DOE/EM. The meeting is not a program review of the individual tasks or subtasks; but instead focuses on the technical aspects and implementation of ESP-sponsored technology or data. The meeting is also attended by members of the ESP Technical Review Team, who have the opportunity at that time to review the ESP as a whole

  1. Meeting of the Technical Working Group on Fast Reactors (TWG-FR) (41st Annual Meeting). Working Material

    International Nuclear Information System (INIS)

    2008-01-01

    The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 40th TWG-FR Annual Meeting, including the status of the actions; - Consider meeting arrangements for 2008, 2009, 2010 and beyond; - Review the IAEA’s ongoing information exchange and coordinated research activities in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives; - Discuss future joint activities in view of IAEA’s Programme and Budget Cycles beyond 2008-2009

  2. Technical and economic limits to fuel burnup extension. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2002-07-01

    For many years, the increase of efficiency in the production of nuclear electricity has been an economic challenge in many countries which have developed this kind of energy. The increase of fuel burnup leads to a reduction in the volume of spent fuel discharged to longer fuel cycles in the reactor, which means bigger availability and capacity factors. After having increased the authorized burnup in plants, developing new alloys capable of resisting high burnup, and having accumulated data on fuel evolution with burnup, it has become necessary to establish the limitations which could be imposed by the physical evolution of the fuel, influencing fuel management, neutron properties, reprocessing or, more generally, the management of waste and irradiated fuels. It is also necessary to verify whether the benefits of lower electricity costs would not be offset by an increase in fuel management costs. The main questions are: Are technical and economic limits to the increasing of fuel burnup in parallel? Can we envisage nowadays the hardest limitation in some of these areas? Which are the main points to be solved from the technical point of view? Is this effort worthwhile considering the economy of the cycle? To which extent? For these reasons, the IAEA, following a recommendation by the International Working Group on Fuel Performance and Technology, held a Technical Committee Meeting on Technical and Economic Limits to Fuel Burnup Extension. The purpose of this meeting was to provide an international forum to review the evolution of fuel properties at increased burnup in order to estimate the limitations both from a physical and an economic point of view. The meeting was therefore divided into two parts. The first part, focusing on technical limits, was devoted to the improvement of the fuel element, such as fission gas release (FGR), RIM effect, cladding, etc. and the fabrication, core management, spent fuel and reprocessing. Eighteen related papers were presented which

  3. 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.

  4. 77 FR 24228 - Proposal Review Panel for Social and Economic Sciences; Notice of Meeting

    Science.gov (United States)

    2012-04-23

    ... following meeting: Name: Site visit review of the Nanoscale Science and Engineering Center (NSEC) at... proprietary or confidential nature, including technical information; financial data, such as salaries and...

  5. IAEA and Iran Hold Technical Meetings in Tehran

    International Nuclear Information System (INIS)

    2014-01-01

    Full text: On 7 and 8 October 2014, the IAEA and the Islamic Republic of Iran held technical meetings within the Framework for Cooperation that was agreed between the parties in November 2013. During the meetings, the two sides held discussions in relation to the implementation of the two practical measures relating to the initiation of high explosives and to neutron transport calculations, agreed in May 2014 in the third step of the Framework for Cooperation. The Agency and Iran will continue discussions on these measures. Iran did not propose any new measures during the meetings in Tehran. Iran and the Agency agreed to meet again, at a date to be announced. (IAEA)

  6. Emerging applications of radiation processing. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2004-01-01

    Approximately 160 gamma irradiators and 1200 electron accelerator based processing units are in operation worldwide. In recent years the IAEA has prepared a directory of industrial gamma irradiators and held several meetings on developments in radiation technology applications. Developments involving the engineering of new sources (both isotope and electrical), high power accelerator applications, etc. have been reported recently, making a review and evaluation of this progress timely. Therefore the IAEA organized a technical meeting in Vienna, Austria, from 28 to 30 April 2003 to review the present situation and the potential contribution of radiation technology to sustainable development. Engineering developments and other features of radiation sources, both isotope and accelerator, were discussed. Recent research has concentrated on three fields: medical and food products, polymers, and environmental pollution control. The stability of radiation sterilized medical implants, as well as the uses of radiation processing for sterilization or decontamination of pharmaceuticals and pharmaceutical raw materials, radiation synthesis and modification of polymers for biomedical applications have been studied. Since separation and enrichment technologies play an important role in product recovery and pollution control, the possibility of radiation synthesis of stimuli-responsive membranes, hydrogels and adsorbents is being investigated. Finally, aside from the technologies for flue gas and wastewater treatment already in use, further research is ongoing on the treatment of organic contaminants in both gaseous and liquid phases. Environmental applications, which also offer new opportunities, should be carefully reviewed to reflect existing regulations and current knowledge. The increasingly serious problem of polyaromatic hydrocarbons (PAH) emissions may be solved in part by the application of radiation technology. This is being studied on a pilot scale for the removal of

  7. Technical Meeting on Grading of the Application of Management System Requirements. Presentations

    International Nuclear Information System (INIS)

    2012-01-01

    The objectives of this Technical Meeting are threefold: - to share international experiences and lessons learned, as well as exchange views on best practices and strategies to overcome the difficulties encountered; - to review and discuss the draft technical report on 'Grading the Application of Management System Requirements, to allow the participants to contribute to the improvement of the document and to enrich it with practical examples; and - to strengthen the international networking of specialists in the field. The topics covered during the meeting will include: - Examples and case studies presented by participants from countries with nuclear facilities (mainly focused on NPPs, and, where appropriate, from research reactors, fuel cycle and waste management facilities) on grading the application of management system requirements and lessons learned. - Reviewing and improving the final draft of a technical report on 'Grading the Application of Management System Requirements', which will supersede the previous guidance: Grading of Quality Assurance Requirement: A Manual (Technical Reports Series No. 328)

  8. [Fortieth Annual] Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

    International Nuclear Information System (INIS)

    2008-01-01

    The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 39th TWG-FR Annual Meeting, including the status of the actions; - Consider meeting arrangements for 2007, 2008 and 2009; - Review the Agency’s ongoing information exchange and co-ordinated research activities in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations; - Discuss future joint activities in view of the Agency’s Programme and Budget Cycle 2008–2009 (and beyond)

  9. Annual technical meeting of the NRC cooperative severe accident research program

    International Nuclear Information System (INIS)

    Silver, E.G.

    1993-01-01

    This brief report summarizes the 1992 annual technical meeting of the NRC Cooperative Severe Accident Research Program (CSARP-92) held at the Hyatt Regency Hotel in Bethesda, Maryland, May 4-8, 1992. The report is taken mainly from coverage of the meeting published in the June 5, 1992, issue of Atomic Energy Clearinghouse. Results of this meeting are formalized at the Water Reactor Safety Information Meetings (WRSIM) that are held annually in October. Nuclear Safety summarizes the annual WRSIM meetings and provides a list of the presentations that were given. Interested readers are encouraged to review listed topics to identify specific topic areas in severe accident research. Sessions were held on in-vessel core melt progression; fuel-coolant interactions; fission-product behavior; direct containment heating; and severe accident code development, assessment, and validation. Summaries of the individual technical sessions and the current state of the art in these areas were given by the chairmen

  10. Research using small tokamaks. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-09-01

    The technical reports in these proceedings were presented at the IAEA Technical Committee Meeting on research Using Small Tokamaks, held in Ahmedabad, India, 6-7 December 1995. The purpose of this annual meeting is to provide a forum for the exchange of information on various small and medium sized plasma experiments, not only for tokamaks. The potential benefits of these research programmes are to: test theories, such as effects of the plasma rotation; check empirical scalings, such as density limits; develop fusion technology hardware; develop plasma diagnostics; such as tomography; and to train scientists, engineers, technicians, and students, particularly in developing IAEA Member States

  11. 76 FR 47613 - Board Meeting: September 13-14, 2011-Salt Lake City, UT; the U.S. Nuclear Waste Technical Review...

    Science.gov (United States)

    2011-08-05

    ...&D Pursuant to its authority under section 5051 of Public Law 100-203, Nuclear Waste Policy... sessions will begin on both days at 8 a.m. and will be held at the Little America Hotel; 500 South Main... rooms has been reserved at the hotel for meeting attendees. To ensure receiving the meeting rate, room...

  12. Forty-Second Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

    International Nuclear Information System (INIS)

    2009-01-01

    The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 41st TWG-FR Annual Meeting, including the status of the actions; - Consider topical technical meetings meeting arrangements for 2009, 2010, 2011 and beyond; - Review the IAEA’s ongoing information exchange and coordinated research activities in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives; - Discuss future joint activities in view of IAEA’s Programme and Budget Cycles beyond 2010-2011

  13. Nuclear power plant diagnostics - Safety aspects and licensing. Report of a technical committee meeting. Working material

    International Nuclear Information System (INIS)

    1997-01-01

    The aim of the Technical Committee Meeting (TCM) was to review developed systems and methods in diagnostics in the scope of their impacts and importance to the safety of Nuclear Power Plants. Papers presented on TCM came from different sources, from developers, from manufacturers, from licensing authorities and from NPP personal. They reflect up to date status in the given subject. Participants of TCM formulated three working groups to elaborate different questions which were raised during the discussions. Their results are reflected in the three chapter titles of the given material. Annex 1 to this document contains presentations made at the Technical Committee Meeting. Refs, figs, tabs

  14. Guidelines for technical reviews of software products

    Energy Technology Data Exchange (ETDEWEB)

    Wilburn, N.P.

    1982-03-01

    A guideline is given for technical review of products developed during a software life cycle. Purposes and benefits of reviews are given. Varieties of reviews, when they should take place, roles of the reviewers and products of the review are described.

  15. Guidelines for technical reviews of software products

    International Nuclear Information System (INIS)

    Wilburn, N.P.

    1982-03-01

    A guideline is given for technical review of products developed during a software life cycle. Purposes and benefits of reviews are given. Varieties of reviews, when they should take place, roles of the reviewers and products of the review are described

  16. Astrobee Periodic Technical Review (PTR) Delta 3

    Science.gov (United States)

    Provencher, Christopher; Smith, Marion F.; Smith, Ernest Everett; Bualat, Maria Gabriele; Barlow, Jonathan Spencer

    2017-01-01

    Astrobee is a free flying robot for the inside of the International Space Station (ISS). The Periodic Technical Review (PTR) delta 3 is the final design review of the system presented to stakeholders.

  17. Proceedings of the efficient separations and processing crosscutting program 1997 technical exchange meeting

    Energy Technology Data Exchange (ETDEWEB)

    Gephart, J.M. [ed.

    1997-05-01

    This document contains summaries of technology development presented at the 1997 Efficient Separations and Processing Crosscutting Program (ESP-CP) Technical Exchange Meeting (TEM), held January 28-30, 1997, in Gaithersburg, Maryland. The ESP-CP is sponsored by the U.S. Department of Energy`s Office of Environmental Management (DOE/EM), Office of Science and Technology. The ESP-CP TEM is held annually to: (1) Present current technology development activities funded by the ESP-CP. Developers of ESP-CP-funded technologies describe the problems and needs addressed by their technologies; the technical approach, accomplishments, and resolution of issues; the strategy and schedule for commercialization; and evolving potential applications. Representatives from DOE/EM`s Focus Areas also present their technology needs. (2) Promote the exchange of technical information among those developing new separations technologies, those responsible for providing new separations technologies to meet DOE/EM needs, and those who need or will potentially make use of such technologies. (3) Familiarize the ESP-CP Technical Review Team with the FY 1997 program and solicit reviewers` views on the program as a whole. This meeting is not a program review of the individual tasks, but instead focuses on the technical aspects and implementation of ESP-CP-sponsored technology or data. This document also contains a list of ESP-CP-sponsored publications, presentations, and patents. Separate abstracts have been indexed into the energy database for contributions to this proceedings.

  18. Proceedings of the efficient separations and processing crosscutting program 1997 technical exchange meeting

    International Nuclear Information System (INIS)

    Gephart, J.M.

    1997-01-01

    This document contains summaries of technology development presented at the 1997 Efficient Separations and Processing Crosscutting Program (ESP-CP) Technical Exchange Meeting (TEM), held January 28-30, 1997, in Gaithersburg, Maryland. The ESP-CP is sponsored by the U.S. Department of Energy's Office of Environmental Management (DOE/EM), Office of Science and Technology. The ESP-CP TEM is held annually to: (1) Present current technology development activities funded by the ESP-CP. Developers of ESP-CP-funded technologies describe the problems and needs addressed by their technologies; the technical approach, accomplishments, and resolution of issues; the strategy and schedule for commercialization; and evolving potential applications. Representatives from DOE/EM's Focus Areas also present their technology needs. (2) Promote the exchange of technical information among those developing new separations technologies, those responsible for providing new separations technologies to meet DOE/EM needs, and those who need or will potentially make use of such technologies. (3) Familiarize the ESP-CP Technical Review Team with the FY 1997 program and solicit reviewers' views on the program as a whole. This meeting is not a program review of the individual tasks, but instead focuses on the technical aspects and implementation of ESP-CP-sponsored technology or data. This document also contains a list of ESP-CP-sponsored publications, presentations, and patents. Separate abstracts have been indexed into the energy database for contributions to this proceedings

  19. Creep-fatigue damage rules for advanced fast reactor design. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-03-01

    The IAEA, following the recommendations of the International Working Group on Fast Reactors, convened a Technical Committee Meeting on Creep-Fatigue Damage Rules to be used in Fast Reactor Design. The objective of the meeting was to review developments in design rules for creep-fatigue conditions and to identify any areas in which further work would be desirable. The meeting was hosted by AEA Technology, Risley, and held in Manchester, United Kingdom, 11-13 June 1996. It was attended by experts from the European Commission, France, India, Japan, the Republic of Korea, the Russian Federation and the United Kingdom. Refs, figs, tabs

  20. Technical Meeting on the Implementation of Fast Reactor Data Retrieval and Knowledge Preservation Activities. Working Material

    International Nuclear Information System (INIS)

    2008-01-01

    The current Technical Meeting was convened to foster the development of the FRKP initiative, in general, and, more specifically, to advance the development of the FRKP Portal. Its objectives were therefore: 1. To review the implementation status of the FRKP Portal prototype; 2. To review the availability of FR-related document collections made accessible through the FRKP Portal; 3. To locate sources of FR-related digital items to be made accessible through the FRKP portal

  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. Proceedings of the technical exchange meeting on passive radon monnitoring

    Energy Technology Data Exchange (ETDEWEB)

    Duray, J.R.; Langner, H. Jr.; Martz, D.E.

    1987-09-01

    The purpose of the meeting was to bring together a number of scientists active in the development and use of passive radon monitoring instrumentation, primarily activated charcoal detectors and alpha track detectors. Many of those present expressed a desire to receive copies of the viewgraphs and other materials presented. Most have supplied extended abstracts or complete reports. These materials are reproduced here as a Technical Measurements Center Report for the benefit of those attending the meeting and for others interested in passive radon monitoring. Individual papers were processed separately for the data base.

  3. Proceedings of the technical exchange meeting on passive radon monnitoring

    International Nuclear Information System (INIS)

    Duray, J.R.; Langner, H. Jr.; Martz, D.E.

    1987-09-01

    The purpose of the meeting was to bring together a number of scientists active in the development and use of passive radon monitoring instrumentation, primarily activated charcoal detectors and alpha track detectors. Many of those present expressed a desire to receive copies of the viewgraphs and other materials presented. Most have supplied extended abstracts or complete reports. These materials are reproduced here as a Technical Measurements Center Report for the benefit of those attending the meeting and for others interested in passive radon monitoring. Individual papers were processed separately for the data base

  4. 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)

  5. 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)

  6. Proceedings of neutron irradiation technical meeting on BNCT

    International Nuclear Information System (INIS)

    2000-10-01

    The 'Neutron Irradiation Technical Meeting for Boron Neutron Capture Therapy (BNCT)' was held on March 13, 2000 at Tokai Research Establishment. The Meeting is aimed to introduce the neutron beam facility for medical irradiation at JRR-4 to Japanese researchers widely, as well as providing an opportunity for young researchers, engineers, medical representatives such surgeons and doctors of pharmacology to present their research activities and to exchange valuable information. JAERI researcher presented the performance and the irradiation technology in the JRR-4 neutron beam facility, while external researchers made various and beneficial presentations containing such accelerator-based BNCT, spectrum-shifter, biological effect, pharmacological development and so on. In this meeting, a special lecture titled 'The Dawn of BNCT and Its Development.' was given by MD, Prof. Takashi Minobe, an executive director of Japan Foundation for Emergency Medicine. The 11 of the presented papers are indexed individually. (J.P.N.)

  7. Proceedings of neutron irradiation technical meeting on BNCT

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-10-01

    The 'Neutron Irradiation Technical Meeting for Boron Neutron Capture Therapy (BNCT)' was held on March 13, 2000 at Tokai Research Establishment. The Meeting is aimed to introduce the neutron beam facility for medical irradiation at JRR-4 to Japanese researchers widely, as well as providing an opportunity for young researchers, engineers, medical representatives such surgeons and doctors of pharmacology to present their research activities and to exchange valuable information. JAERI researcher presented the performance and the irradiation technology in the JRR-4 neutron beam facility, while external researchers made various and beneficial presentations containing such accelerator-based BNCT, spectrum-shifter, biological effect, pharmacological development and so on. In this meeting, a special lecture titled 'The Dawn of BNCT and Its Development.' was given by MD, Prof. Takashi Minobe, an executive director of Japan Foundation for Emergency Medicine. The 11 of the presented papers are indexed individually. (J.P.N.)

  8. Integrated Data Collection Analysis (IDCA) Program — Quarterly Review Meeting

    Energy Technology Data Exchange (ETDEWEB)

    Sandstrom, Mary M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Brown, Geoffrey W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Warner, Kirstin F. [Naval Surface Warfare Center (IHD-NSWC), Indian Head, MD (United States). Indian Head Division; Sorensen, Daniel N. [Naval Surface Warfare Center (IHD-NSWC), Indian Head, MD (United States). Indian Head Division; Remmers, Daniel L. [Naval Surface Warfare Center (IHD-NSWC), Indian Head, MD (United States). Indian Head Division; Shelley, Timothy J. [Air Force Research Lab. (AFRL/RXQF), Tyndall AFB, FL (United States); Reyes, Jose A. [Applied Research Associates, Inc., Tyndall AFB, FL (United States); Phillips, Jason J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hsu, Peter C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Reynolds, John G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2011-12-05

    On November 9 and 10, 2011 the IDCA had the annual quarterly meeting. The meeting started the afternoon of the first day with a tour of the NSWC IHD explosives safety testing and analysis facilities. The meeting on the second day addressed the formal sponsor review and further technical issues for the IDCA. Examination of the IHD equipment during the tour, lead to a long discussion on liquid test methods. The discussion resulted in revision of liquid test methods in the impact test and selection of a new liquid test standard. In addition, modifications to friction, spark and thermal test methods were discussed.

  9. Technical committee meeting on evaluation of radioactive materials release and sodium fires in fast reactors

    International Nuclear Information System (INIS)

    1996-01-01

    The objectives of the Technical Committee Meeting was to review the activities of research on radioactive materials release and sodium fires in fast reactors in each of the participating countries. It covered: out-of-pile experiments and analysis codes on source term; in-pile experiments on source term; core disruptive accidents; sodium leak experience in liquid metal fast reactors; evaluation of sodium fire; and aerosol behaviour

  10. Report on the IAEA technical meeting on application libraries for ADS and transmutation

    International Nuclear Information System (INIS)

    Stanculescu, S.; Trkov, A.

    2004-12-01

    Highlights of the technical meeting are given with respect to the source of evaluated nuclear data, codes for ADS analysis with associated application libraries, content of these libraries, and the procedure for producing them. Participants debated their requirements and formulated an action plan, with work divided between four sub-groups: review/analysis of ADS benchmarks; selection of evaluated nuclear data files; preparation of the cross-section libraries; and benchmarking. Specific tasks were assigned with deadlines. (author)

  11. IAEA technical meeting on nuclear data library for advanced systems - Fusion devices

    International Nuclear Information System (INIS)

    Forrest, R.; Mengoni, A.

    2008-04-01

    A Technical Meeting on 'Nuclear Data Library for Advanced Systems - Fusion Devices' was held at the IAEA Headquarters in Vienna from 31 October to 2 November 2007. The main objective of the initiative has been to define a proposal and detailed plan of activities for a Co-ordinated Research Project on this subject. Details of the discussions which took place at the meeting, including a review of the current activities in the field, a list of recommendations and a proposed timeline schedule for the CRP are summarized in this report. (author)

  12. Assessment of uranium deposit types and resources - A worldwide perspective. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2001-12-01

    The Technical Committee Meeting on Recent Development in Uranium Resources, Production and Demand was held in Vienna from 10 to 13 June 1997. The meeting, held in co-operation with the OECD Nuclear Energy Agency, was successful in bringing together 41 specialists representing 22 Member States and one non-governmental organization (Uranium Institute). A total of 23 papers were presented that report historical reviews and recent developments in the uranium related activities in their respective countries. Each of the papers was indexed separately

  13. 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)

  14. Modelling of Water Cooled Fuel Including Design Basis and Severe Accidents. Proceedings of a Technical Meeting

    International Nuclear Information System (INIS)

    2015-11-01

    The demands on nuclear fuel have recently been increasing, and include transient regimes, higher discharge burnup and longer fuel cycles. This has resulted in an increase of loads on fuel and core internals. In order to satisfy these demands while ensuring compliance with safety criteria, new national and international programmes have been launched and advanced modelling codes are being developed. The Fukushima Daiichi accident has particularly demonstrated the need for adequate analysis of all aspects of fuel performance to prevent a failure and also to predict fuel behaviour were an accident to occur.This publication presents the Proceedings of the Technical Meeting on Modelling of Water Cooled Fuel Including Design Basis and Severe Accidents, which was hosted by the Nuclear Power Institute of China (NPIC) in Chengdu, China, following the recommendation made in 2013 at the IAEA Technical Working Group on Fuel Performance and Technology. This recommendation was in agreement with IAEA mid-term initiatives, linked to the post-Fukushima IAEA Nuclear Safety Action Plan, as well as the forthcoming Coordinated Research Project (CRP) on Fuel Modelling in Accident Conditions. At the technical meeting in Chengdu, major areas and physical phenomena, as well as types of code and experiment to be studied and used in the CRP, were discussed. The technical meeting provided a forum for international experts to review the state of the art of code development for modelling fuel performance of nuclear fuel for water cooled reactors with regard to steady state and transient conditions, and for design basis and early phases of severe accidents, including experimental support for code validation. A round table discussion focused on the needs and perspectives on fuel modelling in accident conditions. This meeting was the ninth in a series of IAEA meetings, which reflects Member States’ continuing interest in nuclear fuel issues. The previous meetings were held in 1980 (jointly with

  15. Results from Consultancy Meeting on Qualified Technical Centres

    International Nuclear Information System (INIS)

    Novakovic, Mladen

    2017-01-01

    Qualified Technical Centres (QTC) - Current Situation: •Many Member States (MS) need help dealing with DSRS; •Most seek assistance, which can include funding, through the IAEA; •Technical assistance is provided by various governmental organization and private companies (service providers = SP). QTC - Method of Delivery Numerous MS requests are pressing the IAEA’s capacity to assist: •Use qualified internal and external experts/contractors; •Limited pool for DSRS and need to expand; •Dedicated and specialized equipment; •Mobile hot cell; •Mobile tool kit; •Field operations; •Coordinated approach with Nuclear Security and Safety. Qualified Technical Centres for the Management of DSRS: •The challenge is to scale up the support for safe and secure management of DSRS; •Strengthen existing capacity of some MS to support others and make support more sustainable; •Expands the support that can be readily provided and meet the many needs of MS

  16. Geothermal Energy and the Eastern US: Technical Information Interchange Meeting, Minutes

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-12-01

    The technical interchange meeting documented here is the fourth meeting where people interested in geothermal energy in the Eastern US have met to interchange technical information. These meetings are intended to assist all in the difficult task of balancing time and effort in doing their assigned jobs and keeping track of what others are doing in similar or related tasks. All of the aforementioned meetings have served their intended purpose and further regional and national meetings are sure to follow.

  17. Geothermal Energy and the Eastern US: Fifth technical information interchange meeting, Minutes

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-12-01

    The technical interchange meeting documented here is the fifth meeting where people interested in geothermal energy in the Eastern US have met to interchange technical information. These meetings are intended to assist all in the difficult task of balancing time and effort in doing their assigned jobs and keeping track of what others are doing in similar or related tasks. All of the aforementioned meetings have served their intended purpose and further regional and national meetings are sure to follow.

  18. 75 FR 19297 - Energy Conservation Program: Public Meeting and Availability of the Preliminary Technical Support...

    Science.gov (United States)

    2010-04-14

    ... Preliminary Technical Support Document for Walk-In Coolers and Walk-In Freezers; Correction and Date Change... April 5, 2010, concerning a public meeting and availability of the preliminary technical support... public meeting and availability of the preliminary technical support document regarding energy...

  19. 77 FR 18243 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC); Notice of Open Meeting

    Science.gov (United States)

    2012-03-27

    ... DEPARTMENT OF ENERGY Hydrogen and Fuel Cell Technical Advisory Committee (HTAC); Notice of Open... open meeting. SUMMARY: This notice announces a meeting of the Hydrogen and Fuel Cell Technical Advisory... Committee: The Hydrogen and Fuel Cell Technical Advisory Committee (HTAC) was established under Section 807...

  20. 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)

  1. Independent technical review of the Pinellas Plant

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    This report documents an Independent Technical Review (ITR) of facilities, organizations, plans, activities and various other elements required to successfully transition the Pinellas Plant from Defense Program (DP) funded operation to either community developed reuse or safe deactivation leading to decontamination and decommissioning (D&D). The review was conducted at the request of the Department of Energy (DOE) Deputy Assistant Secretary for Facility Transition and Management (EM-60) and is a consensus of the nine member ITR Team.

  2. Recycling of plutonium and uranium in water reactor fuel. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-05-01

    The Technical Committee Meeting on Recycling of Plutonium and Uranium in Water Reactor Fuel was recommended by the International Working Group on Fuel Performance and Technology (IWGFPT). Its aim was to obtain an overall picture of MOX fabrication capacity and technology, actual performance of this kind of fuel, and ways explored to dispose of the weapons grade plutonium. The subject of this meeting had been reviewed by the International Atomic Energy Agency every 5 to 6 years and for the first time the problem of weapons grade plutonium disposal was included. The papers presented provide a summary of experience on MOX fuel and ongoing research in this field in the participating countries. The meeting was hosted by British Nuclear Fuels plc, at Newby Bridge, United Kingdom, from 3 to 7 July 1995. Fifty-six participants from twelve countries or international organizations took part. Refs, figs, tabs

  3. 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)

  4. 77 FR 66178 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting...

    Science.gov (United States)

    2012-11-02

    ... Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting; Rescheduled The Sensors and Instrumentation Technical Advisory Committee (SITAC... controls applicable to sensors ] and instrumentation equipment and technology. Agenda Public Session 1...

  5. 78 FR 63161 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting...

    Science.gov (United States)

    2013-10-23

    ... Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting ``Rescheduled'' The Sensors and Instrumentation Technical Advisory Committee (SITAC... controls applicable to sensors and instrumentation equipment and technology. Agenda Public Session 1...

  6. 77 FR 1666 - Information Systems, Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-01-11

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems, Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... information systems equipment and technology. Wednesday, January 25 Open Session 1. Welcome and Introductions...

  7. 75 FR 39919 - Information Systems, Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-07-13

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems, Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... export controls applicable to information systems equipment and technology. Wednesday, July 28 Public...

  8. 76 FR 323 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-01-04

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... export controls applicable to information systems equipment and technology. Wednesday, January 26 Open...

  9. 78 FR 1198 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-01-08

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... to information systems equipment and technology. Wednesday, January 23 Open Session 1. Welcome and...

  10. 78 FR 42753 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-07-17

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... of export controls applicable to information systems equipment and technology. Wednesday, July 31...

  11. 78 FR 63162 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-10-23

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... of export controls applicable to information systems equipment and technology. Wednesday, November 6...

  12. 76 FR 64895 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-10-19

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... export controls applicable to information systems equipment and technology. Wednesday, November 2 Public...

  13. 76 FR 39845 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-07-07

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... export controls applicable to information systems equipment and technology. Wednesday, July 27 Public...

  14. 75 FR 64258 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-10-19

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... export controls applicable to information systems equipment and technology. Wednesday, November 3 Public...

  15. 75 FR 1339 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-01-11

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... export controls applicable to information systems equipment and technology. Wednesday, January 27 Open...

  16. 78 FR 24160 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-04-24

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... controls applicable to information systems equipment and technology. Tuesday, May 7 Open Session 1. Welcome...

  17. 77 FR 37652 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-06-22

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... that affect the level of export controls applicable to information systems equipment and technology...

  18. 77 FR 24178 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-04-23

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... controls applicable to information systems equipment and technology. Tuesday, May 8 Open Session 1. Welcome...

  19. Book Review: New Perspectives on Technical Editing

    Science.gov (United States)

    Murphy, A. J. (Ed.); Sterken, Christiaan

    2012-08-01

    New Perspectives on Technical Editing by Avon J. Murphy (ed.) ISBN : 978-0895033949 (2010) Baywood Publishing Company Inc, Hardcover, 210 pages, 35.5 GBP This book presents a collection of 10 chapters dealing with diverse aspects of technical editing (ie, editorial planning, and analysis and structural changes made to other people's technological documents): research in technical editing, trends and teaching of technical editing, copyediting, and technical journal editing. The role and function of the modern journal and book editor is also dealt with in detail. Each chapter is written by an expert in the field: senior editors, university professors in technical communication, technical writers and linguists. The ever-evolving role of the editor is clearly elucidated in several historical reviews, and in the descriptions of the expectations for the future. A very striking aspect of this book is its extensive collection of bibliographic resources: every chapter lists dozens of very useful references, and the closing chapter, and annotated bibliography, contain many not so well known references, and are most useful. All in all, the book is a treasure trove listing more than 400 references, in addition to numerous webpage URLs embedded in the texts. The book is designed to help the reader to understand current practices and norms in technical editing, and to help to take action in editing as well as in teaching and educating would-be editors. The audience for this book thus includes editors and teachers, but also writers, researchers and students. A deep reading of this book will result in a better understanding of the difference between full technical editing and its much narrower component so well known as copyediting, and will convince any prospective editor that editing should not be undertaken if the people involved do not master the art of precision and accuracy in technical (as well as in human) communication, do not possess the technical know how and computer

  20. Technical Meeting on Impact of Fukushima Event on Current and Future Fast Reactor Designs. Working Material

    International Nuclear Information System (INIS)

    2012-01-01

    The overall purpose of the Technical Meeting was to recognize and analyse the implications of the accident occurred at the Fukushima Dai-ichi Nuclear Power Station on current and future fast neutron systems design and operation. The aim was to provide a global forum for discussing the principal lessons learned from this event, and thus to review safety principles and characteristics of existing and future fast neutron concepts, especially in relation with extreme natural events which potentially may lead to severe accident scenarios. The participants also presented and discussed innovative technical solutions, design features and countermeasures for design extension conditions - including earthquakes, tsunami and other extreme natural hazards - which can enhance the safety level of existing and future fast neutron systems. Furthermore, the meeting gave the opportunity to present advanced methods for the evaluation of the robustness of plants against design extension conditions. Another important goal of this TM was to discuss how to harmonize safety approaches and goals for next generation’s fast reactors. Finally, the meeting was intended to identify areas where further research and development in nuclear safety, technology and engineering in the light of the Fukushima accident are needed. In the frame of the implementation of its Nuclear Safety Action Plan endorsed by all Member States, the IAEA will consider these areas as potential technical topics for new Coordinated Research Projects, to be launched in the near future

  1. Forty-Fifth Annual Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Presentations

    International Nuclear Information System (INIS)

    2012-01-01

    The objectives of the meeting were to: • Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); • Review the progress since the 44 th TWG-FR Annual Meeting, including the status of the actions; • Consider topical technical meeting arrangements for 2012-2013, as well as review FR-related activities included in the IAEA Programme & Budget (P&B) biennium 2012-2013; • Review the IAEA’s concluded, on-going and planned coordinated research projects in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives (GIF, INPRO, NEA, ESNII, etc.)

  2. Subsurface barrier feasibility evaluation: External review meeting report

    International Nuclear Information System (INIS)

    Lindberg, S.L.; Rouse, J.K.

    1994-12-01

    The Westinghouse Hanford Company -- Tank Waste Remediation System Division (TWRS) Program is evaluating subsurface barrier technologies for potential use in supporting remediation of the Hanford Tank Farms for the US Department of Energy, Richland Operations Office (DOE-RL). An External Review Team (ERT) was assembled to perform an independent technical review of the work performed to-date supporting the evaluation process. A set of draft documents was forwarded to the ERT for their review, and a meeting was held August 10 through 12, 1994, to facilitate comments and resolutions. This document summarizes the meeting, the comments provided by the ERT, and the ongoing work to resolve the comments and support a pending decision by The US Department of Energy, Richland Operations Office; the Washington State Department of Ecology; and the US Environmental Protection Agency

  3. Summary report of an IAEA technical meeting on International Code Centres Network

    International Nuclear Information System (INIS)

    Clark, R.E.H.

    2009-02-01

    Eleven international experts on computational aspects of atomic, molecular and particle surface interaction data for fusion energy research participated in a technical meeting to initiate an International Code Centres Network. The participants reviewed the capabilities and future directions in their computational efforts at their institutions. Different methods of accessing the computational facilities were discussed, and a proposed method of linking efforts was formulated. A consensus was reached on forming a flexible organization with the ability to adjust and adapt to future needs of the fusion community as new experimental devices are developed, requiring different priorities of data generation. (author)

  4. 76 FR 20948 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-04-14

    ... Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory Committee (SITAC) will meet on... applicable to sensors ] and instrumentation equipment and technology. Agenda Public Session 1. Welcome and...

  5. 77 FR 61737 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-10-11

    ... Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory Committee (SITAC) will meet on... applicable to sensors and instrumentation equipment and technology. Agenda Public Session 1. Welcome and...

  6. 76 FR 323 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-01-04

    ... Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory Committee (SITAC) will meet on... applicable to sensors and instrumentation equipment and technology. Agenda: Public Session: 1. Welcome and...

  7. 78 FR 60251 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-10-01

    ... Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory Committee (SITAC) will meet on... applicable to sensors and instrumentation equipment and technology. ] Agenda Public Session 1. Welcome and...

  8. 75 FR 62508 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-10-12

    ... Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory Committee (SITAC) will meet on... applicable to sensors and instrumentation equipment and technology. Agenda Public Session 1. Welcome and...

  9. 77 FR 2270 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-01-17

    ... Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory Committee (SITAC) ] will meet on... applicable to sensors and instrumentation equipment and technology. Agenda Public Session 1. Welcome and...

  10. 78 FR 1198 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-01-08

    ... Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory Committee (SITAC) will meet on... applicable to sensors and instrumentation equipment and technology. Agenda Public Session 1. Welcome and...

  11. 75 FR 39920 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-07-13

    ... Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory Committee (SITAC) will meet on... applicable to sensors and instrumentation equipment and technology. Agenda Public Session 1. Welcome and...

  12. 77 FR 23222 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-04-18

    ... Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory Committee (SITAC) will meet on... applicable to sensors and instrumentation equipment and technology. Agenda Public Session 1. Welcome and...

  13. 75 FR 1339 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-01-11

    ... Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory Committee (SITAC) will meet on... applicable to sensors and instrumentation equipment and technology. Agenda Public Session 1. Welcome and...

  14. 78 FR 40098 - Sensors And Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-07-03

    ... Bureau of Industry and Security Sensors And Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory Committee (SITAC) will meet on... applicable to sensors and instrumentation equipment and technology. Agenda Public Session 1. Welcome and...

  15. 78 FR 19638 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-04-02

    ... Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory Committee (SITAC) will meet on... applicable to sensors and instrumentation equipment and technology. Agenda Public Session 1. Welcome and...

  16. 75 FR 14426 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-03-25

    ... Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory Committee (SITAC) will meet on... applicable to sensors and instrumentation equipment and technology. Agenda Public Session 1. Welcome and...

  17. 77 FR 37652 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-06-22

    ... Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory Committee (SITAC) will meet on... applicable to sensors and instrumentation equipment and technology. Agenda Public Session: 1. Welcome and...

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

    International Nuclear Information System (INIS)

    Forrest, R.; Dunaeva, S.; Otsuka, N.

    2010-07-01

    This report summarizes the IAEA Technical Meeting of the International Network of Nuclear Reaction Data Centres (biennial Data Centre Heads Meeting), held at the Japan Nuclear Reaction Data Centre, Hokkaido University, Sapporo, Japan, from 20 - 23 April 2010. The meeting was attended by 27 participants from 12 cooperating data centres of seven 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. This report summarizes the IAEA Technical Meeting of the International Network of Nuclear Reaction Data Centres (biennial Data Centre Heads Meeting), held at the Japan Nuclear Reaction Data Centre, Hokkaido University, Sapporo, Japan, from 20 - 23 April 2010. The meeting was attended by 27 participants from 12 cooperating data centres of seven 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)

  19. Studies on fuels with low fission gas release. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-10-01

    For more than a decade, the IAEA has organized various specialists meetings to discuss advances in nuclear fuel technology for non-water cooled reactors. In order to review progress in research and development of fuels with low fission gas release for light water reactors, fast reactors and research reactors, an IAEA Technical Committee meeting was organized in October 1996. At the invitation of the Government of the Russian Federation, the meeting was held in Moscow. Experts from seven Member States and one international organization participated. The objective of the meeting was to exchange topical information on such fuels, to evaluate their advantages and drawbacks, and to explore their commercial utilization. The present volume contains the full text of the sixteen papers presented at the meeting. The information compiled in these proceedings should be useful for engineers, scientists and managers from nuclear fuel development organizations, fuel fabrication plants, utilities and regulatory bodies who are involved in the analysis of fuel behaviour under normal and accident conditions. Refs, figs, tabs

  20. Poolside inspection, repair and reconstitution of LWR fuel elements. Proceedings of a Technical Committee meeting

    International Nuclear Information System (INIS)

    1998-11-01

    The Technical Committee Meeting on Poolside Inspection, repair and reconstruction of LWR Fuel Elements was organize by IAEA upon the recommendations of the International Working Group on Fuel performance Technology and held in Switzerland in October 1997. The purpose of the Meeting was to review the state of art in the area of poolside inspection, repair and reconstruction of light water fuel elements and to evaluate the progress achieved in this area since previous IAEA Meetings on the same topic in 1981 and 1984. The Meeting provided a forum on exchange of information between utilities, fuel designers and other authorities and specialists on a topic of current interest and real concern to industries in many Member States. The respective technologies are widely used or planned to be used in order to identify elementary major causes of fuel failure and to improve fuel utilization by repair and subsequent reuse of fuel elements. The Proceedings includes papers presented at the Meeting each described by a separate abstract

  1. Conceptual designs of advanced fast reactor. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1996-10-01

    A Technical Committee meeting (TCM) was held on Conceptual Designs of Advanced Fast Power Reactors to review the lessons learned from the construction and operation of demonstration and near-commercial size plants. This TCM focused on design and development of advanced fast reactors and identified methodologies to evaluate the economic competitiveness and reliability of advanced projects. The Member States which participated in the TCM were at different stages of LMFR development. The Russian Federation, Japan and India had prototype and/or experimental LMFRs and continue with mature R and D programmes. China, the Republic of Korea and Brazil were at the beginning of LMFR development. Therefore the aims of the TCM were to obtain technical descriptions of different design approaches for experimental, prototype, demonstration and commercial LMFRs, and to describe the engineering judgements made in developing the design approaches. Refs, figs, tabs

  2. Report on the Technical Meeting on Therapeutic Radiopharmaceuticals

    International Nuclear Information System (INIS)

    2009-01-01

    The purpose of the TM was to provide an experts' platform to facilitate exploring the current status and future directions on therapeutic radiopharmaceuticals. The invited talks and presentations in the TM were in the following topics: - Radionuclide Production; - Production and availability of alpha emitters and their radiopharmaceuticals; - Therapeutic radiopharmaceutical chemistry; - Targets and biological evaluation; - Medical physics and dosimetry; - Clinical applications including radioimmunotherapy and clinical needs; - Peptide receptor mediated therapy Panel discussions: - Radionuclide therapy using alpha emitters; - Regulatory challenges with therapeutic radiopharmaceuticals; - International activities in radionuclide therapy. he technical meeting generated a large interest among scientists and physicians working in the field of targeted therapy using radiopharmaceuticals. Participants from both developed and developing MS reported on recent developments on the research work and clinical studies going on in the field and provided their views on the future developments in this field. The unexpected high number of participants and the high number of presentations with exceptional quality underlines the great interest of scientists and professionals in therapeutic applications using radiolabelled drugs / biomolecules. The intensive discussions including panels specified the challenges in the future on developing novel agents and to finally use them for the benefit of patients. The IAEA can play as vital role in streamlining developments and to provide tools to overcome scientific, professional and regulatory challenges in the field of therapeutic radiopharmaceuticals

  3. 76 FR 21043 - Notice of Public Meeting: Technical Aspects of Mandatory Deposit of Published Electronic Works...

    Science.gov (United States)

    2011-04-14

    ... Copyright Office Notice of Public Meeting: Technical Aspects of Mandatory Deposit of Published Electronic Works Available Only Online AGENCY: U.S. Copyright Office, Library of Congress. ACTION: Notice of public meeting. SUMMARY: The U.S. Copyright Office of the Library of Congress will host a public meeting on May...

  4. Gas turbine power conversion systems for modular HTGRs. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    2001-08-01

    The Technical Committee Meeting (TCM) on Gas Turbine Power Conversion Systems for Modular HTGRs held in Palo Alto, California, USA was convened by the IAEA on the recommendation of its International Working Group on Gas Cooled Reactors (IWGGCR). The meeting was attended by 27 participants from 9 Member States (Argentina, China, France, Japan, Netherlands, Russian Federation, South Africa, United Kingdom and the United States of America). In addition to presentations on relevant technology development activities in participating Member States, 16 technical papers were presented covering the areas of: Power conversion system design; Power conversion system analysis; and Power conversion system component design. A panel discussion was held on technology issues associated with gas turbine modular HTGR power conversion systems and the potential for international collaboration to address these issues. The purpose of this Technical Committee Meeting was to foster the international exchange of information and perspectives on gas turbine power conversion systems and components for modular HTGRs. The overall objectives were to provide: a current overview of designs under consideration; information on the commercial availability or development status of key components; exchange of information on the issues involved and potential solutions; identification of further development needs for both initial deployment and longer term performance enhancement, and the potential for addressing needs through international collaboration. The following conclusions and recommendations were identified as a result of the discussions at the meeting. International review and collaboration is of interest for China and Japan in the planning and conduct of their test programs: both the HTTR and HTR-10 reactor projects are exploring scale model testing of a gas turbine, with the HTTR project considering a 7 MWt gas heated loop, and HTR-10 a direct or indirect cycle connected to the reactor; the HTR

  5. Immunization review meetings: "Low Hanging Fruit" for capacity building and data quality improvement?

    Science.gov (United States)

    Shimp, Lora; Mohammed, Nassor; Oot, Lisa; Mokaya, Evans; Kiyemba, Timothy; Ssekitto, Gerald; Alminana, Adriana

    2017-01-01

    Although systematic program review meetings are common practice in many health and immunization programs, there is little documentation on their implementation and role. Adult education principles espouse opportunities for peer exchange to build capacity and cross-learning, for which review meetings have been a forum utilized in immunization programs for many years. This study describes the process and use of review meetings to build immunization technical capacity in four African countries since 2011. A longitudinal case study providing retrospective descriptive analysis and qualitative data collected on immunization program implementation and review meetings conducted within the years of 2011-2016 with district and facility health staff and technical partners from Ethiopia, Kenya, Tanzania and Uganda. Based on summarized findings and analyses from over 200 review meetings conducted in the four countries within the time period of 2011-2016, these meetings have been shown to be effective tools for improving immunization program performance and the capacity of health staff. Review meetings (ideally conducted quarterly) provide health workers with beneficial and low cost opportunities for adult learning, including building skills in data analysis and review, which can be sustained at district and health facility levels. In combination with other performance improvement approaches implemented and supported in countries (such as supportive supervision, training, and on-the-job learning and assessment), review meetings can also contribute to achievement of immunization and health outcomes.

  6. Outcomes of the First Review Meeting of the Joint Convention

    International Nuclear Information System (INIS)

    Linsley, G.

    2003-01-01

    The First Review Meeting of the Joint Convention was held from 3 to 14 November 2003 in Vienna. It was attended by representatives of 33 Contracting Parties (350 persons registered). The scope of applications includes: Waste and spent fuel from the operation of NPPs; Waste from use of radionuclides in medicine and industry; Spent sealed sources; Discharges from regulated nuclear facilities; Waste from mining and processing of uranium. The content of the Joint Convention and obligation of the Contracting Parties are reviewed in the report. The review process is also described. The effectiveness of review mechanism is discussed. Some technical issues are also discussed, such as: the wide variety of long term spent fuel and radioactive waste management policies; clearance; decommissioning; regulatory independence; discharges to the environment; Management of disused sealed sources etc. Some good practices have been identified and comments are given

  7. Technical meeting on commercial applications of nuclear analytical techniques. Meeting report

    International Nuclear Information System (INIS)

    2004-01-01

    This report summarizes the findings of the Technical Meeting on the Commercial Applications of Nuclear Analytical Techniques held in Vienna on 23-26 November 2004, where an assessment was initiated of the world capacity and market potentials for neutron activation analysis and nuclear spectroscopy, including an estimation of economic revenues. Industry and governmental agencies were identified as stakeholders for these laboratories. Examples are given of potential benefits of these techniques to the stakeholders. The potentials for commercial applications of neutron activation analysis and nuclear spectroscopy (measurement of alpha, beta and gamma ray emitting radionuclides) are addressed. First estimates are given of the worldwide capacity of these laboratories, suggestions and examples are given for potential markets and the typical organizational and technical constraints are discussed. Two case studies of commercial neutron activation analysis laboratories at a small and a medium-size reactor are given in the 'individual contributions' section of this document. An assessment of other nuclear analytical techniques such as X ray Fluorescence Spectrometry, Particle Induced X ray Emission Spectrometry or Ion Beam Analysis Spectrometry has been completed after a comprehensive collection of background information

  8. Forty-Sixth Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

    International Nuclear Information System (INIS)

    2013-01-01

    The objectives of the meeting were to: • Review the current status and the progress since the 45th TWG-FR meeting of FR and ADS technology development activities in IAEA Member States; • Review the activities (past, present and planned) of the IAEA’s project 1.1.5.3, “Support for fast reactor research, technology development and deployment” to ensure that they remain relevant to the needs of Member States; • Provide the experts group with updates to advise the IAEA on FR and ADS activities, including on proposals for relevant studies and reviews; • Serve as a means for exchanging information on national and international FR and ADS programmes; • Review the main achievements and outcomes of the “International Conference on Fast Reactors and Related Fuel Cycle: Safe Technologies and Sustainable Scenarios – FR13”, held on 4 – 7 March 2013 in Paris, France; • Promote the exchange of technical information by proposing topics for, and assisting in the organization of, IAEA Workshops and Technical Meetings for 2014-2015 and further, and • Review the IAEA’s concluded, on-going and planned coordinated research projects (CRPs) in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives (GIF, INPRO, NEA, Euratom, etc.)

  9. High temperature gas cooled reactor technology development. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-12-01

    The successful introduction of an advanced nuclear power plant programme depends on many key elements. It must be economically competitive with alternative sources of energy, its technical development must assure operational dependability, the support of society requires that it be safe and environmentally acceptable, and it must meet the regulatory standards developed for its use and application. These factors interrelate with each other, and the ability to satisfy the established goals and criteria of all of these requirements is mandatory if a country or a specific industry is to proceed with a new, advanced nuclear power system. It was with the focus on commercializing the high temperature gas cooled reactor (HTGR) that the IAEA's International Working Group on Gas Cooled Reactors recommended this Technical Committee Meeting (TCM) on HTGR Technology Development. Over the past few years, many Member States have instituted a re-examination of their nuclear power policies and programmes. It has become evident that the only realistic way to introduce an advanced nuclear power programme in today's world is through international co-operation between countries. The sharing of expertise and technical facilities for the common development of the HTGR is the goal of the Member States comprising the IAEA's International Working Group on Gas Cooled Reactors. This meeting brought together key representatives and experts on the HTGR from the national organizations and industries of ten countries and the European Commission. The state electric utility of South Africa, Eskom, hosted this TCM in Johannesburg, from 13 to 15 November 1996. This TCM provided the opportunity to review the status of HTGR design and development activities, and especially to identify international co-operation which could be utilized to bring about the commercialization of the HTGR

  10. Independent technical review of the Mound Plant

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    This report documents an Independent Technical Review (ITR) of the facilities, organizations, plans, and activities required to transition particular elements of the Mound Plant from Defense Program (DP) funded operation as appropriate either to community developed reuse or safe deactivation leading to decontamination and decommissioning (D&D). The review was conducted at the request of the Dr. Willis Bixby, Deputy Assistant Secretary, U.S. Department of Energy EM-60, Office of Facility Transition and Management and is a consensus of the nine member ITR Team. Information for the review was drawn from documents provided to the ITR Team by the Miamisburg Area Office (MB) of the DOE, EG&G, the City of Miamisburg, and others; and from presentations, discussions, interviews, and facility inspections at the Mound Plant during the weeks of March 14 and March 28, 1994. During the week of April 25, 1994, the ITR Team met at Los Alamos, New Mexico to develop consensus recommendations. A presentation of the core recommendations was made at the Mound Plant on May 5, 1994. This is an independent assessment of information available to, and used by, the Mound Plant personnel. Repetition of the information is not meant to imply discovery by the ITR Team. Team members, however, acting as independent reviewers, frequently assess the information from a perspective that differs significantly from that of the Mound Plant personnel. The report is based on information obtained and conditions observed during the March 1994 review interval. The ITR process and normal site work often initiate rapid, beneficial changes in understanding and organization immediately following the review. These changes frequently alter conditions observed during the review, but the report does not address changes subsequent to the review interval.

  11. WIND ENERGY CONVERSION SYSTEMS - A TECHNICAL REVIEW

    Directory of Open Access Journals (Sweden)

    N. RAMESH BABU

    2013-08-01

    Full Text Available Wind power production has been under the main focus for the past decade in power production and tremendous amount of research work is going on renewable energy, specifically on wind power extraction. Wind power provides an eco-friendly power generation and helps to meet the national energy demand when there is a diminishing trend in terms of non-renewable resources. This paper reviews the modeling of Wind Energy Conversion Systems (WECS, control strategies of controllers and various Maximum Power Point Tracking (MPPT technologies that are being proposed for efficient production of wind energy from the available resource.

  12. Proceedings of the technical meetings 'Water, radioactivity and environment'

    International Nuclear Information System (INIS)

    Perceval, Olivier; Foulquier, Luc; Canneva, Guillem; Jedor, Beatrice; Genthon, Benedicte; Vicaud, Alain; Skrzypczak, Julien; Gibeaux, Audrey; Phrommavanh, Vannapha; Descostes, Michael; Tognelli, Antoine; Calmet, Dominique; Leprieur, Fabrice; Pignol, David; Thybaud, Eric; Feray, Christine; Leclerc, Elisabeth; Maitre, Melanie; Calmon, Philippe; Marang, Laura; Beaugelin-Seiller, Karine; Garnier-Laplace, Jacqueline; Leprieur, Fabrice; Philippot, Benoit; Hemidy, Pierre-Yves; Devin, Patrick; Perrier, Gilles; CALVEZ, Marianne; Descamps, E.; Preveral, S.; Brutesco, C.; Ginet, N.; Escofier, C.; Garcia, D.; Pignol, D.; Ansaldi, M.; Rodrigue, A.; Bazin, I.; Cholat, P.; Bailly-Du-Bois, Pascal; Fievet, Bruno; Godinot, Claire; Eyrolle-Boyer, Frederique; Antonelli, Christelle; Tournieux, Damien; Augeray, Celine; Galliez, Kevin; Baconet, I.; Cavaliere, N.; Dias Varela, D.; Foulon, L.; Laconici, C.; Lorand, H.; Mouton, M.; Siscard, N.; Tarlette, L.; Loyen, Jeanne; Gleizes, Marc; Vidal, R.; Borgia, Cecile; Hemidy, Pierre-Yves; Fouchet, Loic; Gontier, G.; Grignard, G.; Drozdzak, Jegodz; Leermakers, Martine; Brun, Frederic; Ameon, Roselyne; Gleizes, Marc; Maulard, Alain; Moine, Jerome; Tchilian, Nathalie; Paillard, Herve; Gaid, Abdelkader; Wittmann, Erich; Boucherie, Christophe; Devin, Patrick

    2014-12-01

    These technical days were organized by the 'Environment section' of the French Society of Radiation Protection (SFRP). Their aim was to review the current state of water use, management and monitoring, in particular in the nuclear industry, both on the radiological and chemical aspects. This document brings together the available presentations (slides) together with their corresponding abstracts (in French) and dealing with: 1 - Environmental issues linked to water and aquatic ecosystems contamination by micropollutants (O. Perceval); 2 - 50 years of radioecology in aquatic environments (L. Foulquier); 3 - Regulation and organisation of the French administration for water and aquatic ecosystems management (G. Canneva); 4 -European and French regulations about the radiological quality of drinking water (B. Jedor); 5 - Water samplings and liquid effluents from nuclear facilities: regulation, authorisations, prescriptions (B. Genthon); 6 - Water needs of a NPP (A. Vicaud); 7 - Water management at old uranium mining sites (A. Gibeaux); 8 - Mobile system for liquid effluents treatment (J. Skrzypczak); 9 - Water: an essential vector for the transfer of radioactive and chemical compounds in the underground (A. Tognelli); 10 - Environmental guide values for aquatic ecosystems protection (E. Thybaud); 11 - Prioritisation work for radioactive and chemical compounds to be monitored in aquatic environments in the framework of the environment perennial lab (E. Leclerc); 12 - Liquid radioactive effluents in continental aquatic environments: why and how estimating the impact? (K. Beaugelin-Seiller); 13 - Sustainable water management: standards, a compulsory tool (D. Calmet); 14 - Water sampling: from theory to practice (F. Leprieur, B. Philippot); 15 - Prototype for the detection of toxic compounds in the environment (D. Pignol); 16 - Nuclear metrology and water: new available and developing techniques (C. Augeray, K. Galliez); 17 - Measurement of the uranium and radium bio

  13. Report on the IAEA technical meeting on network of nuclear reaction data centres

    International Nuclear Information System (INIS)

    Pronyaev, V.G.; Schwerer, O.; Nichols, A.L.

    2002-08-01

    An IAEA Technical Meeting on the Network of Nuclear Reaction Data Centres (and the biennial Data Centre Heads' Meeting) was held at the OECD Nuclear Energy Agency, Issy-les-Moulineaux (near Paris), France, from 27 to 30 May 2002. The meeting was attended by 21 participants from 12 co-operating data centres of six Member States and two international organizations. This report contains the meeting summary, conclusions and actions, status reports of the participating data centres, and working papers considered. (author)

  14. Report on the IAEA technical meeting on network of nuclear reaction data centres

    International Nuclear Information System (INIS)

    Schwerer, O.

    2006-12-01

    An IAEA Technical Meeting on the Network of Nuclear Reaction Data Centres (biennial Data Centre Heads Meeting) was held at IAEA Headquarters, Vienna, Austria, from 25 to 28 September 2006. The meeting was attended by 19 participants from 10 cooperating data centres of six Member States and two international organizations. A summary of the meeting is given in this report, along with the conclusions, actions, and status reports of the participating data centres. (author)

  15. 78 FR 6854 - Health Services Research and Development Service Scientific Merit Review Board; Notice of Meeting

    Science.gov (United States)

    2013-01-31

    ... DEPARTMENT OF VETERANS AFFAIRS Health Services Research and Development Service Scientific Merit... Research and Development Service Scientific Merit Review Board will meet on February 13-14, 2013, at the... research. Applications are reviewed for scientific and technical merit. Recommendations regarding funding...

  16. Technical minutes of the ninth INDC meeting. Vienna, 16-20 May 1977

    International Nuclear Information System (INIS)

    Motz, H.

    1978-05-01

    Progress reports from data centres on data measurements, facilities and evaluations, on coordinating activities are presented along with reports of technical, ad-hoc and policy subcommittees, on plans for cooperation and past meetings

  17. The 1996 meeting of the national technical workgroup on mixed waste thermal treatment

    International Nuclear Information System (INIS)

    1996-01-01

    The National Technical Workgroup on Mixed Waste Thermal Treatment held its annual meeting in Atlanta Georgia on March 12-14, 1996. The National Technical Workgroup (NTW) and this meeting were sponsored under an interagency agreement between EPA and DOE. The 1996 Annual Meeting was hosted by US DOE Oak Ridge Operations in conjunction with Lockheed Martin Energy Systems - Center for Waste Management. A new feature of the annual meeting was the Permit Writer Panel Session which provided an opportunity for the state and federal permit writers to discuss issues and potential solutions to permitting mixed waste treatment systems. In addition, there was substantial discussion on the impacts of the Waste Combustion Performance Standards on mixed waste thermal treatment which are expected to proposed very soon. The 1996 meeting also focussed on two draft technical resource documents produced by NTW on Waste Analysis Plans and Compliance Test Procedures. Issues discussed included public involvement, waste characterization, and emission issues

  18. Radiation treatment of gaseous and liquid effluents for contaminant removal. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2005-12-01

    The Technical Meeting on Radiation Processing of Gaseous and Liquid Effluents conducted in Sofia, Bulgaria, 7-10 September 2004, discussed and evaluated issues related to the status and future trends in radiation application for environmental protection. Five experts from Bulgaria, India, the Republic of Korea, Poland, and the United States of America were invited to provide their experiences in this field. Twenty cost-free participants and observers - from Bulgaria, India, Lithuania, Poland and Ukraine -joined the meeting, and 15 papers in total were presented. Research and development in radiation processing of gaseous and liquid effluents is undertaken in three fields: electron beam flue gas treatment (SO x and NO x removal), wastewater purification and sewage sludge sterilization. Wastewater or sludge treatment and flue gas purification all differ from technological points of view, but they are common services and applications of environmental radiation technology applications, based mostly on electron accelerators. The technical meeting discussed new development in the field of radiation applications in environmental service, especially the status and prospects of radiation processing of gaseous and liquid effluents. Progress in the field of electron accelerators and gamma sources is crucial for routine application of the technology. Cost reduction and improvement of technical reliability are substantial especially for high power of accelerators and high activity of the sources needed for environmental applications. Environmental applications were carefully reviewed in accordance with the existing regulations and state of the art knowledge. The comparison with conventional commercial technologies was addressed as well. In flue gas treatment, applicability of the technology using different fossil fuels (coal, lignite, oil, etc.) was reviewed. The elaborated materials cover the technical and economical evaluation of the technologies. The possible applications of

  19. Regulatory surveillance of safety related maintenance at nuclear power plants. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-08-01

    The operational safety and reliability of a nuclear power plant as well as its availability for electricity generation depend on, among other things, its maintenance programme. Regulatory bodies therefore have considerable interest in maintenance activities. There are several approaches to maintenance, i.e. reliability centered maintenance or risk focused maintenance, aimed at optimizing maintenance by focusing on important components or systems. These approaches may result in significant changes to maintenance activities and therefore have to be considered for regulatory acceptance. In order to review and discuss the status of maintenance regulation in participating countries, the IAEA convened a Technical Committee Meeting on Regulatory Oversight of Maintenance Activities at Nuclear Power Plants in Vienna from 9 to 13 October 1995. The meeting was attended by 16 experts from 11 countries. In addition to the consideration of papers that were presented and which are reproduced here, extensive group and panel discussions took place during the meeting. These covered three main topics: general features and basic characteristics of maintenance regulation, regulatory acceptance of maintenance optimization and use of PSA for maintenance optimization. The discussion are summarized in Section 2. Section 3 discusses the following three additional topics: regulatory involvement in the maintenance programme, modifications to the maintenance programme and personnel related aspects of maintenance. The conclusions are presented in Section 4. Figs, tabs

  20. Fuel Behaviour and Modelling under Severe Transient and Loss of Coolant Accident (LOCA) Conditions. Proceedings of a Technical Meeting

    International Nuclear Information System (INIS)

    2013-06-01

    In recent years the demands on 'fuel duties' have increased, including transient regimes, higher burnups and longer fuel cycles. To satisfy these demands, fuel vendors have developed and introduced new cladding and fuel material designs to provide sufficient margins for safe operation of the fuel components. National and international experimental programmes have been launched, and models have been developed or adapted to take into account the changed conditions. These developments enable water cooled reactors, which contribute about 95% of the nuclear power in the world today, to operate safely under all operating conditions; moreover, even under severe transient or accident conditions, such as reactivity initiated accidents (RIAs) or loss of coolant accidents (LOCAs), the behaviour of the fuel can be adequately predicted and the consequences of such events can be safely contained. In 2010 the IAEA Technical Working Group on Fuel Performance and Technology (TWGFPT) recommended that a technical meeting on ''Fuel Behaviour and Modelling under Severe Transient and LOCA Conditions'' be held in Japan. The accident at the Fukushima Daiichi nuclear power plant in March 2011 highlighted the need to address this subject, and despite the difficult situation in Japan at the time, the recommended plan was confirmed, and the Japan Atomic Energy Agency (JAEA) hosted the technical meeting in Mito, Ibaraki Prefecture, Japan, from 18 to 21 October 2011. This meeting was the eighth in a series of IAEA meetings, which reflects Member States' continuing interest in the above issues. The previous meetings were held in 1980 (jointly with OECD Nuclear Energy Agency, Helsinki, Finland), 1983 (Riso, Denmark), 1986 (Vienna, Austria), 1988 (Preston, United Kingdom), 1992 (Pembroke, Canada), 1995 (Dimitrovgrad, Russian Federation) and 2001 (Halden, Norway). The purpose of the technical meeting was to provide a forum for international experts to review the current situation and the state of

  1. MEETING REPORT: OMG Technical Committee Meeting in Orlando, FL, sees significant enhancement to CORBA

    Science.gov (United States)

    1998-06-01

    The Object Management Group (OMG) Platform Technology Committee (PTC) ratified its support for a new asynchronous messaging service for CORBA at OMG's recent Technical Committee Meeting in Orlando, FL. The meeting, held from 8 - 12 June, saw the PTC send the Messaging Service out for a final vote among the OMG membership. The Messaging Service, which will integrate Message Oriented Middleware (MOM) with CORBA, will give CORBA a true asynchronous messaging capability - something of great interest to users and developers. Formal adoption of the specification will most likely occur by the end of the year. The Messaging Service The Messaging Service, when adopted, will be the world's first standard for Message Oriented Middleware and will give CORBA a true asynchronous messaging capability. Asynchronous messaging allows developers to build simpler, richer client environments. With asynchronous messaging there is less need for multi-threaded clients because the Asynchronous Method Invocation is non-blocking, meaning the client thread can continue work while the application waits for a reply. David Curtis, Director of Platform Technology for OMG, said: `This messaging service is one of the more valuable additions to CORBA. It enhances CORBA's existing asynchronous messaging capabilities which is a feature of many popular message oriented middleware products. This service will allow better integration between ORBs and MOM products. This enhanced messaging capability will only make CORBA more valuable for builders of distributed object systems.' The Messaging Service is one of sixteen technologies currently being worked on by the PTC. Additionally, seventeen Revision Task Forces (RTFs) are working on keeping OMG specifications up to date. The purpose of these Revision Task Forces is to take input from the implementors of OMG specifications and clarify or make necessary changes based on the implementor's input. The RTFs also ensure that the specifications remain up to date

  2. Minutes of Technical Division Steering Committee meeting, November 21, 1955 -- Savannah River Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Evans, L.C.

    1955-11-21

    The topics discussed at this meeting included: the approval for six technical studies, safety concerns, fuel elements for tritium production, and the Mark III fuel assembly. Appendices attached to this report describe the financial status [unreadable], the theoretical physics program, experimental physics program, pile engineering program, and the Technical Division study status.

  3. Unusual occurrences during LMFR operation. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2000-10-01

    Design of liquid metal cooled fast reactors (LMFRs) is still in evolution, and only a small number of LMFRs are in operation around the world. Specialists operating these LMFRs have gained valuable experience from incidents, failures, and other events that took place in the reactors. These unusual occurrences, lessons learned and measures undertaken to prevent recurrences are often either not reported in the literature, or reported only briefly and without sufficient detail. Hence there is a need for specialists designing and operating LMFRs to share their knowledge on unusual occurrences. Considerable experimental and theoretical knowledge in this field were collected by several Member states over the past decades. The needs in generalisation, review and documentation of fundamental knowledge in liquid metal cooled reactor technology were a major consideration in the recommendation by the International Working group on fast reactors for the IAEA to convene this Technical Committee meeting on the subject of unusual occurrences during LMFR operation and the consequences for reactor systems

  4. 78 FR 58534 - Warm Springs Irrigation District; Notice of Technical Meeting

    Science.gov (United States)

    2013-09-24

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13570-002] Warm Springs Irrigation District; Notice of Technical Meeting a. Project Name and Number: Warm Springs Dam Hydroelectric Project No. 13570 b. Date and Time of Meeting: October 1, 2013; 11:00 a.m. Pacific Time (2:00 p.m. Eastern...

  5. 77 FR 43592 - Public Utility District No. 1 of Snohomish County, WA; Notice of Technical Meeting

    Science.gov (United States)

    2012-07-25

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Public Utility District No. 1 of Snohomish County, WA; Notice of Technical Meeting a. Date, Time and Place of Meeting: Monday, August 6, 2012 starting at 9 a.m. Pacific Time (12...

  6. 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.

  7. Technical meeting on 'Primary coolant pipe rupture event in liquid metal cooled fast reactors'. Working material

    International Nuclear Information System (INIS)

    2003-01-01

    In Liquid Metal cooled Fast Reactors (LMFR) or in accelerator driven sub-critical systems (ADS) with LMFR like sub-critical cores, the primary coolant pipes (PCP) connect the primary coolant pumps to the grid plate. A rupture in one of these pipes could cause significant loss of coolant flow to the core with severe consequences. In loop type reactors, all primary pipelines are provided with double envelopes and inter-space coolant leak monitoring systems that permit leak detection before break. Thus, the PCP rupture event can be placed in the beyond design basis event (BDBE) category. Such an arrangement is difficult to incorporate for pool type reactors, and hence it could be argued that the PCP rupture event needs to be analysed in detail as a design basis event (DBE, category 4 event). The primary coolant pipes are made of ductile austenitic stainless steel material and operate at temperatures of the cold pool and at comparatively low pressures. For such low stressed piping with negligible creep and embrittlement effects, it is of interest to discuss under what design provisions, for pool type reactors, the guillotine rupture of PCP could be placed in the BDBE category. The topical Technical Meeting (TM) on 'Primary Coolant Pipe Rupture Event in Liquid Metal Cooled Reactors' was called to enable the specialists to present the philosophy and analyses applied on this topic in the various Member States for different LMFRs. The scope of the Technical Meeting was to provide a global forum for information exchange on the philosophy applied in the various participating Member States and the analyses performed for different LMFRs with regard to the primary coolant pipe rupture event. More specifically, the objectives of the Technical Meeting were to review the safety philosophy for the PCP rupture event in pool type LMFR, to assess the structural reliability of the PCP and the probability of rupture under different conditions (with/without in-service inspection), to

  8. Proceedings of the 18th technical meeting on nuclear reactor and radiation for KURRI engineers and the 9th technical official group section 5 meeting in Kyoto University

    International Nuclear Information System (INIS)

    2010-03-01

    This report is a summary of 18th Technical Meeting on Nuclear Reactor and Radiation for KURRI Engineers in Kyoto University. This was also the 9th meeting for technical official group section 5 (nuclear and radiation) in Kyoto University. In the workshop, three special lectures held were: (1) 'On Border Between Subcritical and Supercritical', (2) 'Memories of Nuclear Power Plant Management for 40 Years', and (3) 'Introduction of Technical Office in Faculty of Engineering, Kyoto University'. The technical presentations held were: (1) 'Radiation Background Study of Specialty Products in Senshu Region', (2) 'Introduction of Radioactivation Analysis at KUR', (3) 'Consideration of Critical Approach Method for KUR Low-Enrichment Fuel Reactor Core Using SRAC', (4) 'Evaluation of Temperature Coefficient of KUR Low-Enrichment Fuel Reactor Core Using SRAC'. As training for technical staffs in Technical Office, we visited the facility in Ashiu Research Forest. An introduction of this facility and the comments from the participants were included in this report. (S.K.)

  9. Nuclear data for the International Fusion Materials Irradiation Facility (IFMIF). Summary report of technical meeting

    International Nuclear Information System (INIS)

    Forrest, R.; Mengoni, A.

    2005-10-01

    Experts on reaction cross-section databases participated in a Technical Meeting organized at the Forschungszentrum Zentrum (FZK), Karlsruhe, Germany on 4-6 October 2005. The overall objective of the meeting was to explore the possibilities for improving the status of the nuclear database for the assessment of radiation damage to structural components of large fusion devices. The discussions and recommendations of the meeting are briefly described in this report. (author)

  10. Report on the IAEA technical meeting on the network of nuclear reaction data centres

    International Nuclear Information System (INIS)

    Schwerer, O.

    2006-02-01

    Results of the IAEA Technical meeting on the Network of Nuclear Reaction Data Centres held at the IAEA Headquarters, Vienna, Austria, 12 to 14 October 2005, are summarized in this report. The meeting was attended by 16 participants from 11 co-operating data centres of six Member States and two International Organizations. The report contains a summary of the meeting, the conclusions and actions, and status reports of the participating data centres. (author)

  11. 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)

  12. Proceedings of the black liquor research program review fifth meeting

    Energy Technology Data Exchange (ETDEWEB)

    1988-09-01

    On June 14--17, 1988 the participants and invited guests of the Cooperative Program in Kraft Recovery gathered in Charleston, South Carolina, to review progress on four major black liquor research programs being executed at the Institute of Paper Chemistry, the University of Maine, the National Bureau of Standards, and the University of Florida. These programs include: (1) Black Liquor Properties; (2) Black Liquor Droplet Formation; (3) Black Liquor Nozzle Evaluation; and (4) Black Liquor Combustion. In addition to the objectives of previous meetings, this meeting made a direct attempt to gather ideas on how to improve our ability to move from new technology concepts to commercial implementation. Also attached is the agenda for the Charleston meeting. The first two days were involved with updates and reviews of the four major black liquor programs. A half day was spent discussing pathways to implementation and developing thoughts on what industry, DOE and academia could do to facilitate commercial implementation of the research results. This publication is a summary of the presentations made in Charleston and the industry responses to the research work. Readers are cautioned that the contents are in-progress updates on the status of the research and do not represent referred technical papers. Any questions regarding the content should be referred to the principal investigators of the project.

  13. Signal processing and electronics for nuclear spectrometry. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2009-12-01

    electronics and digital signal processing methods are enabling advances in numerous spectrometry applications such as lightweight, portable and hand held radiation instruments, and high-resolution digital medical imaging systems. The objective of this technical meeting was to review the current status, developments and trends in nuclear electronics and signal processing, and their application with various radiation detectors. The meeting discussed the problems faced and the solutions employed, to improve the performances of data acquisition systems and high-tech equipment used for nuclear spectrometry. Presentations made at the meeting elaborated operational experiences with modern signal processing and electronics, and highlighted the latest developments in this field. This publication summarizes the findings and conclusions arising from this technical meeting

  14. NASA Technical Interchange Meeting (TIM): Advanced Technology Lifecycle Analysis System (ATLAS) Technology Tool Box

    Science.gov (United States)

    ONeil, D. A.; Craig, D. A.; Christensen, C. B.; Gresham, E. C.

    2005-01-01

    The objective of this Technical Interchange Meeting was to increase the quantity and quality of technical, cost, and programmatic data used to model the impact of investing in different technologies. The focus of this meeting was the Technology Tool Box (TTB), a database of performance, operations, and programmatic parameters provided by technologists and used by systems engineers. The TTB is the data repository used by a system of models known as the Advanced Technology Lifecycle Analysis System (ATLAS). This report describes the result of the November meeting, and also provides background information on ATLAS and the TTB.

  15. University Research Consortium annual review meeting program

    International Nuclear Information System (INIS)

    1996-07-01

    This brochure presents the program for the first annual review meeting of the University Research Consortium (URC) of the Idaho National Engineering Laboratory (INEL). INEL is a multiprogram laboratory with a distinctive role in applied engineering. It also conducts basic science research and development, and complex facility operations. The URC program consists of a portfolio of research projects funded by INEL and conducted at universities in the United States. In this program, summaries and participant lists for each project are presented as received from the principal investigators

  16. University Research Consortium annual review meeting program

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-07-01

    This brochure presents the program for the first annual review meeting of the University Research Consortium (URC) of the Idaho National Engineering Laboratory (INEL). INEL is a multiprogram laboratory with a distinctive role in applied engineering. It also conducts basic science research and development, and complex facility operations. The URC program consists of a portfolio of research projects funded by INEL and conducted at universities in the United States. In this program, summaries and participant lists for each project are presented as received from the principal investigators.

  17. Primary coolant pipe rupture event in liquid metal cooled reactors. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2004-08-01

    In liquid-metal cooled fast reactors (LMFR) the primary coolant pipes (PCP) connect the primary coolant pumps to the grid plate. A rupture in one of these pipes could cause significant loss of coolant flow to the core with severe consequences. In loop type reactors, all primary pipelines are provided with double envelopes and inter-space coolant leak monitoring systems that permit leak detection before break. Thus, the PCP rupture event can be placed in the beyond design basis event (BDBE) category. Such an arrangement is difficult to incorporate for pool type reactors, and hence it could be argued that the PCP rupture event needs to be analysed in detail as a design basis event (DBE, category 4 event). However, the primary coolant pipes are made of ductile austenitic stainless steel material and operate at temperatures of the cold pool and at comparatively low pressures. For such low stressed piping with negligible creep and embrittlement effects, it is of interest to discuss under what design provisions, for pool type reactors, the guillotine rupture of PCP could be placed in the BDBE category. The topical Technical Meeting (TM) on Primary Coolant Pipe Rupture Event in Liquid Metal Cooled Reactors (Indira Gandhi Centre for Atomic Research, Kalpakkam, India, 13-17 January 2003) was called to enable the specialists to present the philosophy and analyses applied on this topic in the various Member States for different LMFRs. The scope of the technical meeting was to provide a global forum for information exchange on the philosophy applied in the various participating Member States and the analyses performed for different LMFRs with regard to the primary coolant pipe rupture event. More specifically, the objectives of the technical meeting were to review the safety philosophy for the PCP rupture event in pool type LMFR, to assess the structural reliability of the PCP and the probability of rupture under different conditions (with/without in-service inspection), to

  18. INFOTECH `92: DOE Technical Information (TI) Meeting, October 21--23, 1992

    Energy Technology Data Exchange (ETDEWEB)

    Blanton, J.M.

    1992-10-01

    This proceedings contains papers presented at the 1992 Department of Energy (DOE) Technical Information Meeting held at the Office of Scientific and Technical Information (OSTI), Oak Ridge, Tennessee, October 21--23, 1992. It is composed of written presentation given orally at the meeting in either large-group or break-out sessions. The proceedings is provided as a reference tool for those who attended the meeting as well as an information document for those unable to attend. The annual DOE Technical Information meeting is designed for information professionals involved in the management of the Department`s scientific and technical information (STI). Speakers include members of the OSTI staff as well as DOE and DOE contractors and other invited specialists in the field of information. The major objective of the meeting is to provide a forum within the Department for discussing current and future information policies, trends, and management techniques as well as the technologies and standards available for managing and accessing scientific and technical information.

  19. Chernobyl: 30 years after - Proceedings of the technical meeting of the French Society of Radiation Protection

    International Nuclear Information System (INIS)

    Champion, Didier; Chouha, Michel; Damette, Guy; Durand, Vanessa; Besnus, Francois; Renaud, Philippe; Adam-Guillermin, Christelle; Laurier, Dominique; Chabrier, Patrick; Chauveau, Thomas; Thiry, Yves; Menetrier, Florence; Chevillard, Sylvie; Lesueur, Fabienne; Schneider, Thierry

    2016-03-01

    The French Society of Radiation Protection (SFRP) organized a technical meeting on the present day situation of the Chernobyl site, 30 years after the accident of the nuclear power plant. The review deals with the situation of the facility and of its safety works, the environment, the management of wastes, the workers and populations exposure, and the health monitoring of the exposed populations. This document brings together the abstracts and the presentations (slides) of the different talks given at the meeting: 1 - The main highlights 30 years after the Chernobyl accident (Didier CHAMPION, SFRP); 2 - Circumstances, progress and consequences of the Chernobyl accident - Lessons and experience feedback for the other RBMK reactors (Michel CHOUHA, IRSN); 3 - Chernobyl, a confinement arch for 100 years (Patrick CHABRIER, Thomas CHAUVEAU - BOUYGUES); 4 - The reactor wastes management and the dismantling operations (Guy DAMETTE - IRSN); 5 - Environment contamination in the vicinity of the site (Yves THIRY - ANDRA); 6 - Impact of the accident on agriculture (Vanessa DURAND - IRSN); 7 - The fate of remediation wastes (Francois BESNUS - IRSN); 8 - Chernobyl fallouts in France (Philippe RENAUD - IRSN); 9 - The ecological consequences of the Chernobyl accident (Christelle ADAM-GUILLERMIN - IRSN); 10 - Results of liquidators and populations exposure (Florence MENETRIER - CEA); 11 - Thyroid cancers monitoring in the Chernobyl area and the role of modifying genetic factors (Fabienne LESUEUR - Institut Curie); 12 - Results of the Chernobyl accident health impact studies (Dominique LAURIER - IRSN); 13 - Impact on populations living condition (Thierry SCHNEIDER - CEPN); 14 - Molecular signature of radiation induced thyroid tumors (Sylvie CHEVILLARD - CEA)

  20. State technical review of the HLNW program and the peer review process

    International Nuclear Information System (INIS)

    Jacob, G.R.

    1986-01-01

    Millions of dollars are being spent on state governments' review of the Department of Energy (DOE) high level waste (HLW) repository program. A significant portion of the review efforts focus on technical issues surrounding the development and installment of HLW disposal technologies. Some view the states' technical review efforts as part of a peer review process. However, this interpretation reveals a misunderstanding of the concept of peer review and the purposes of state technical review

  1. Instrumentation for Digital Nuclear Spectroscopy. Proceedings of the IAEA Technical Meeting

    International Nuclear Information System (INIS)

    2013-06-01

    and reliability of data delivered are increased and advances and new applications in handheld field instruments, and in remote and unattended nuclear spectrometry systems, are also enabled. The objective of this technical meeting is to provide a forum for researchers and various industrial partners involved in the development of nuclear spectrometry to share best practices and practical experiences in the design, use and implementation of digital pulse processing in nuclear spectrometry. The meeting reviewed the state of the art and current trends in the field of digital pulse processing, the advantages and limitations, end user demands and future prospects. This publication summarizes the findings and conclusions arising from this technical meeting

  2. 78 FR 18680 - Rehabilitation Research and Development Scientific Merit Review Board, Notice of Meeting

    Science.gov (United States)

    2013-03-27

    ... DEPARTMENT OF VETERANS AFFAIRS Rehabilitation Research and Development Scientific Merit Review... Service, and the Chief Research and Development Officer on the scientific and technical merit, the mission... Committee Act, 5 U.S.C. App. 2, that a meeting of the Rehabilitation Research and Development Service...

  3. Practices and developments in spent fuel burnup credit applications. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2003-10-01

    The International Atomic Energy Agency convened a technical committee Meeting on Requirements, Practices and Developments in Burnup Credit (BUC) Applications in Madrid, Spain, from 22 to 26 April 2002. The purpose of this meeting was to explore the progress and status of international activities related to the BUC applications for spent nuclear fuel. This meeting was the third major meeting on the uses of BUC for spent fuel management systems held since the IAEA began to monitor the uses of BUC in spent fuel management systems in 1997. The first major meeting was an Advisory Group meeting (AGM), which was held in Vienna, in October 1997. The second major meeting was a technical committee meeting (TCM), which was held in Vienna, in July 2000. Several consultants meetings were held since 1997 to advise and assist the IAEA in planning and conducting its BUC activities. The proceedings of the 1997 AGM were published as IAEA-TECDOC-1013, and the proceedings of the 2000 TCM as IAEA-TECDOC-1241. BUC for wet and dry storage systems, spent fuel transport, reprocessing and final disposal is needed in many Member States to allow for increased enrichment, and to increase storage capacities, cask capacities and dissolver capacities avoiding the need for extensive modifications. The use of BUC is a necessity for spent fuel disposal

  4. Proceedings of the Advanced Turbine Systems annual program review meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

    Goals of the 8-year program are to develop cleaner, more efficient, and less expensive gas turbine systems for utility and industrial electric power generation, cogeneration, and mechanical drive units. During this Nov. 9-11, 1994, meeting, presentations on energy policy issues were delivered by representatives of regulatory, industry, and research institutions; program overviews and technical reviews were given by contractors; and ongoing and proposed future projects sponsored by university and industry were presented and displayed at the poster session. Panel discussions on distributed power and Advanced Gas Systems Research education provided a forum for interactive dialog and exchange of ideas. Exhibitors included US DOE, Solar Turbines, Westinghouse, Allison Engine Co., and GE.

  5. A COMPREHENSIVE TECHNICAL REVIEW OF THE DEMONSTRATION BULK VITRIFICATION SYSTEM

    Energy Technology Data Exchange (ETDEWEB)

    SCHAUS, P.S.

    2006-09-29

    In May 2006, CH2M Hill Hanford Group, Inc. chartered an Expert Review Panel (ERP) to review the current status of the Demonstration Bulk Vitrification System (DBVS). It is the consensus of the ERP that bulk vitrification is a technology that requires further development and evaluation to determine its potential for meeting the Hanford waste stabilization mission. No fatal flaws (issues that would jeopardize the overall DBVS mission that cannot be mitigated) were found, given the current state of the project. However, a number of technical issues were found that could significantly affect the project's ability to meet its overall mission as stated in the project ''Justification of Mission Need'' document, if not satisfactorily resolved. The ERP recognizes that the project has changed from an accelerated schedule demonstration project to a formally chartered project that must be in full compliance with DOE 413.3 requirements. The perspective of the ERP presented herein, is measured against the formally chartered project as stated in the approved Justification of Mission Need document. A justification of Mission Need document was approved in July 2006 which defined the objectives for the DBVS Project. In this document, DOE concluded that bulk vitrification is a viable technology that requires additional development to determine its potential applicability to treatment of a portion of the Hanford low activity waste. The DBVS mission need statement now includes the following primary objectives: (1) process approximately 190,000 gallons of Tank S-109 waste into fifty 100 metric ton boxes of vitrified product; (2) store and dispose of these boxes at Hanford's Integrated Disposal Facility (IDF); (3) evaluate the waste form characteristics; (4) gather pilot plant operability data, and (5) develop the overall life cycle system performance of bulk vitrification and produce a comparison of the bulk vitrification process to building a second LAW

  6. A COMPREHENSIVE TECHNICAL REVIEW OF THE DEMONSTRATION BULK VITRIFICATION SYSTEM

    International Nuclear Information System (INIS)

    SCHAUS, P.S.

    2006-01-01

    In May 2006, CH2M Hill Hanford Group, Inc. chartered an Expert Review Panel (ERP) to review the current status of the Demonstration Bulk Vitrification System (DBVS). It is the consensus of the ERP that bulk vitrification is a technology that requires further development and evaluation to determine its potential for meeting the Hanford waste stabilization mission. No fatal flaws (issues that would jeopardize the overall DBVS mission that cannot be mitigated) were found, given the current state of the project. However, a number of technical issues were found that could significantly affect the project's ability to meet its overall mission as stated in the project ''Justification of Mission Need'' document, if not satisfactorily resolved. The ERP recognizes that the project has changed from an accelerated schedule demonstration project to a formally chartered project that must be in full compliance with DOE 413.3 requirements. The perspective of the ERP presented herein, is measured against the formally chartered project as stated in the approved Justification of Mission Need document. A justification of Mission Need document was approved in July 2006 which defined the objectives for the DBVS Project. In this document, DOE concluded that bulk vitrification is a viable technology that requires additional development to determine its potential applicability to treatment of a portion of the Hanford low activity waste. The DBVS mission need statement now includes the following primary objectives: (1) process approximately 190,000 gallons of Tank S-109 waste into fifty 100 metric ton boxes of vitrified product; (2) store and dispose of these boxes at Hanford's Integrated Disposal Facility (IDF); (3) evaluate the waste form characteristics; (4) gather pilot plant operability data, and (5) develop the overall life cycle system performance of bulk vitrification and produce a comparison of the bulk vitrification process to building a second LAW Immobilization facility or other

  7. 7. IAEA Technical Meeting on Steady State Operation of Magnetic Fusion Devices - Booklet of abstracts

    International Nuclear Information System (INIS)

    2015-01-01

    This meeting has provided an appropriate forum to discuss current issues covering a wide range of technical topics related to the steady state operation issues and also to encourage forecast of the ITER performances. The technical meeting includes invited and contributed papers. The topics that have been dealt with are: 1) Superconducting devices (ITER, KSTAR, Tore-Supra, HT-7U, EAST, LHD, Wendelstein-7-X,...); 2) Long-pulse operation and advanced tokamak physics; 3) steady state fusion technologies; 4) Long pulse heating and current drive; 5) Particle control and power exhaust, and 6) ITER-related research and development issues. This document gathers the abstracts

  8. Safety of and regulations for nuclear fuel cycle facilities. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    2001-05-01

    In order to compile information on the nature of the safety concerns and current status of the regulations concerning nuclear fuel cycle facilities in Member States, an IAEA Technical Committee meeting on this topic was convened from 8 to 12 May 2000 in Vienna. The present publication contains the results of this meeting. The contributions of the participants in Annex 3 exemplify the work done in some Member States to develop an adequate regulatory framework to oversee the safe operation of these facilities

  9. Technical Change in the North American Forestry Sector: A Review

    Science.gov (United States)

    Jeffery C. Stier; David N. Bengston

    1992-01-01

    Economists have examined the impact of technical change on the forest products sector using the historical, index number, and econometric approaches. This paper reviews econometric analyses of the rate and bias of technical change, examining functional form, factors included, and empirical results. Studies are classified as first- second-, or third-generation...

  10. Water Chemistry and Clad Corrosion/Deposition Including Fuel Failures. Proceedings of a Technical Meeting

    International Nuclear Information System (INIS)

    2013-03-01

    Corrosion is a principal life limiting degradation mechanism in nuclear steam supply systems, particularly taking into account the trends in increasing fuel burnup, thermal ratings and cycle length. Further, many plants have been operating with varying water chemistry regimes for many years, and issues of crud (deposition of corrosion products on other surfaces in the primary coolant circuit) are of significant concern for operators. At the meeting of the Technical Working Group on Fuel Performance and Technology (TWGFPT) in 2007, it was recommended that a technical meeting be held on the subject of water chemistry and clad corrosion and deposition, including the potential consequences for fuel failures. This proposal was supported by both the Technical Working Group on Advanced Technologies for Light Water Reactors (TWG-LWR) and the Technical Working Group on Advanced Technologies for Heavy Water Reactors (TWG-HWR), with a recommendation to hold the meeting at the National Nuclear Energy Generating Company ENERGOATOM, Ukraine. This technical meeting was part of the IAEA activities on water chemistry, which have included a series of coordinated research projects, the most recent of which, Optimisation of Water Chemistry to Ensure Reliable Water Reactor Fuel Performance at High Burnup and in Ageing Plant (FUWAC) (IAEATECDOC-1666), concluded in 2010. Previous technical meetings were held in Cadarache, France (1985), Portland, Oregon, USA (1989), Rez, Czech Republic (1993), and Hluboka nad Vltavou, Czech Republic (1998). This meeting focused on issues associated with the corrosion of fuel cladding and the deposition of corrosion products from the primary circuit onto the fuel assembly, which can cause overheating and cladding failure or lead to unplanned power shifts due to boron deposition in the clad deposits. Crud deposition on other surfaces increases radiation fields and operator dose and the meeting considered ways to minimize the generation of crud to avoid

  11. Robotics Collaborative Technology Alliance (RCTA): Technical Exchange Meeting (TEM) 2015

    Science.gov (United States)

    2017-05-01

    for this collection of information is estimated to average 1 hour per response, including the time for reviewing instructions, searching existing... estimate or any other aspect of this collection of information, including suggestions for reducing the burden, to Department of Defense, Washington...radiation waves not in the visible spectrum through the use of infrared transceivers (Arvin et al. 2009), ultrasonic sensors (Kim and Kim 2013), and

  12. Summary report of IAEA technical meeting: 15. meeting of the IFRC Subcommittee on Atomic and Molecular Data for Fusion

    International Nuclear Information System (INIS)

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

    2007-02-01

    The 15th Meeting of the Subcommittee on Atomic and Molecular Data for Fusion of the International Fusion Research Council was held on 20-21 April 2006, at the IAEA Headquarters in Vienna, Austria. Work of the Atomic and Molecular Data Unit for the period 2004-2006 was reviewed, and recommendations were made for the 2008-2009 budget cycle. The proceedings, conclusions and recommendations of the Subcommittee meeting are briefly described in this report. Specific recommendations of the Subcommittee from this meeting, as well as the report on the activities of the IAEA Atomic and Molecular Data Unit for the period June 2004 - March 2006, are also included. (author)

  13. Tanks Focus Area FY98 midyear technical review

    Energy Technology Data Exchange (ETDEWEB)

    Schlahta, S.N.; Brouns, T.M.

    1998-06-01

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

  14. Tanks Focus Area FY98 midyear technical review

    International Nuclear Information System (INIS)

    Schlahta, S.N.; Brouns, T.M.

    1998-06-01

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

  15. Efficient separations and processing crosscutting program 1996 technical exchange meeting. Proceedings

    International Nuclear Information System (INIS)

    1996-01-01

    This document contains summaries of technology development presented at the 1996 Efficient Separations and Processing Crosscutting Program Technical Exchange Meeting. This meeting is held annually to promote a free exchange of ideas among technology developers, potential users and other interested parties within the EM community. During this meeting the following many separation processes technologies were discussed such as ion exchange, membrane separation, vacuum distillation, selective sorption, and solvent extraction. Other topics discussed include: waste forms; testing or inorganic sorbents for radionuclide and heavy metal removal; selective crystallization; and electrochemical treatment of liquid wastes. This is the leading abstract, individual papers have been indexed separately for the databases

  16. Efficient separations and processing crosscutting program 1996 technical exchange meeting. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-02-01

    This document contains summaries of technology development presented at the 1996 Efficient Separations and Processing Crosscutting Program Technical Exchange Meeting. This meeting is held annually to promote a free exchange of ideas among technology developers, potential users and other interested parties within the EM community. During this meeting the following many separation processes technologies were discussed such as ion exchange, membrane separation, vacuum distillation, selective sorption, and solvent extraction. Other topics discussed include: waste forms; testing or inorganic sorbents for radionuclide and heavy metal removal; selective crystallization; and electrochemical treatment of liquid wastes. This is the leading abstract, individual papers have been indexed separately for the databases.

  17. Safety and environmental aspects of partitioning and transmutation of actinides and fission products. Proceedings of a technical committee meeting held in Vienna, 29 November - 2 December 1993

    International Nuclear Information System (INIS)

    1995-01-01

    There is considerable interest in many countries in the partitioning and transmutation of long lived radionuclides as a potential complement to the closed fuel cycle. Recognizing this, the IAEA organized a Technical Committee Meeting on Safety and Environmental Aspects of Partitioning and Transmutation of Actinides and Fission Products, to review the current status of progress of national and international programmes and identify the most important directions of co-operation. The results of the Technical Committee meeting are presented in this document. Refs, figs and tabs

  18. 75 FR 23223 - Meetings of the Agricultural Policy Advisory Committee for Trade and the Agricultural Technical...

    Science.gov (United States)

    2010-05-03

    ... Foreign Agricultural Service Meetings of the Agricultural Policy Advisory Committee for Trade and the Agricultural Technical Advisory Committees for Trade AGENCY: Foreign Agricultural Service, USDA. ACTION: Notice... compromise the development by the U.S. government of trade policy priorities, negotiating objectives, or...

  19. IAEA technical committee meeting on research using small fusion devices (abstracts)

    International Nuclear Information System (INIS)

    1999-12-01

    The thirteenth IAEA technical committee meeting on research using small fusion devices are held in Chengdu, P. R. China on 18-20 Oct. , 1999. 41 articles are received and the content includes toroidal systems, helical systems, plasma focus, diagnostic systems, theory and modeling, improving confinement, numerical simulation, innovative concepts and others

  20. 75 FR 79017 - Notice of Public Meeting, North Slope Science Initiative-Science Technical Advisory Panel

    Science.gov (United States)

    2010-12-17

    .... Update on the project tracking system, database and public Web site. NSSI priority recommendations on... Bureau of Land Management Notice of Public Meeting, North Slope Science Initiative--Science Technical Advisory Panel AGENCY: Bureau of Land Management, Alaska State Office, North Slope Science Initiative...

  1. Advances in heavy water reactor technology. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-11-01

    This IAEA meeting addressed both the status of national programmes and technical topics including advances in plant and system design and new plant features, development of pressure tube technologies, fuel and fuel cycle options, computer code development and verification, and safety and accident analysis

  2. 76 FR 63607 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-10-13

    ...] [FR Doc No: 2011-26009] DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation... that affect the level of export controls applicable to sensors and instrumentation equipment and...

  3. Use of probabilistic safety assessment in the regulatory process. Report of the technical committee meeting. Working material

    International Nuclear Information System (INIS)

    1994-01-01

    A Technical Committee Meeting (TCM) was organized between 5-8 December 1994 to discuss and review the international situation in connection with the use made, whether formally or informally, by regulatory bodies of probabilistic safety assessment (PSA) in the course of their work, and the related question of the use and value of adopting probabilistic safety criteria (PSC) as an aid to judging the results of PSAs. The document includes the output from the four working groups, as well as 11 papers from the 12 papers presented to the TCM. A separate abstract was prepared for each paper. Refs, figs, tabs

  4. Technical meeting on 'Operational and decommissioning experience with fast reactors'. Working material

    International Nuclear Information System (INIS)

    2002-01-01

    to accommodate changing objectives and boundary conditions. This flexibility can only be assured with the deployment of the fast neutron spectrum reactor technology, and reprocessing. At the same time that the interest in the fast reactor waned, also the retirement of many of the developers of this technology reached its peak, between 1990 and 2000, and hiring diminished in parallel. Moreover, R and D programs are being discontinued, and facilities falling in disuse. Under these circumstances, the loss of the fast reactor knowledge base should be taken seriously. One particularly important aspect of this knowledge base is given by the accumulated operational experience. The participants in the 33rd Annual Meeting of the International Working Group on Fast Reactors, 'Technical Committee Meeting on Liquid Metal Fast Reactor Developments' (Vienna, 16-18 May 2000), recommended holding a technical meeting (TM) on 'Feedback from Operational and Decommissioning Experience with Fast Reactors'. At the 34th Annual Meeting of the Technical Working Group on Fast Reactors, 'Technical Committee Meeting on Review of National Programmes on Fast Reactors and ADS' (Almaty/Kurchatov City, Kazakhstan, 14-18 May 2001), it was further recommended to launch a Coordinated Research Program (CRP) on 'Generalisation and Analyses of Operational Experience with Fast Reactor Equipment and Systems' (Preserve Fast Reactor Operation and Decommissioning Experience). It was agreed to structure the TM in such a way that, apart from providing an information exchange opportunity, it would also prepare the grounds for the CRP. The scope of the TM was to provide a global forum for information exchange on fast reactor operational and decommissioning experience. The objectives of the TM were to: exchange detailed technical information on fast reactor operation and/or decommissioning experience with DFR, PFR (UK); KNK-II (Germany); Rapsodie, Phenix, Superphenix (France); BR-10, BOR-60, BN-600 (Russia); BN-350

  5. 76 FR 38383 - Albany Engineering Corporation, Town of Stuyvesant, NY; Notice of Site Visit and Technical Meeting

    Science.gov (United States)

    2011-06-30

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [ Project No. 2696-033] Albany..., Office of Energy Projects staff will participate in a site visit and technical meeting for the Stuyvesant Falls Hydroelectric Project (FERC No. 2696-033). The purpose of the site visit and technical meeting is...

  6. 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)

  7. Physics and technology of inertial fusion energy targets chambers and drivers. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2005-09-01

    The third IAEA Technical Meeting on Physics and Technology of Inertial Fusion Energy Targets and Chambers took place 11-13 October 2004 in the Yousung Hotel Daejon, Republic of Korea. The first meeting was held in Madrid, Spain, 7-9 June 2000, and the second one in San Diego, California, 17-19 June 2002. Nuclear fusion has the promise of becoming an abundant energy source with good environmental compatibility. Excellent progress has been made in controlled nuclear fusion research on both magnetic and inertial approaches for plasma confinement. The IAEA plays a pro-active role to catalyze innovation and enhance worldwide commitment to fusion. This is done by creating awareness of the different concepts of magnetic as well as inertial confinement. The International Fusion Research Council (IFRC) supports the IAEA in the development of strategies to enhance fusion research in Member States. As part of the recommendations, a technical meeting on the physics and technology of inertial fusion energy (IFE) was proposed in one of the council meetings. The objective of the technical meeting was to contribute to advancing the understanding of targets and chambers for all proposed inertial fusion energy power plant designs. The topics to be covered were: Target design and physics, chamber design and physics, target fabrication injection and Tritium handling, assessment of safety, environment and economy aspect of IFE. It was recognized by the International Advisory Committee that the scope of the meeting should also include fusion drivers. The presentations of the meeting included target and chamber physics and technology for all proposed IFE plant concepts (laser driven, heavy-ion driven, Z-pinches, etc.). The final Research Coordination Meeting of the Coordinated Research Project on Elements of Power Plant Design for Inertial Fusion Energy, including further new results and achievements, followed the technical meeting. Twenty-nine participants from 12 countries participated

  8. 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)

  9. IAEA Technical Meeting on Innovative Heat Exchanger and Steam Generator Designs for Fast Reactors. Presentations

    International Nuclear Information System (INIS)

    2011-01-01

    The fast reactor, which can generate electricity and breed additional fissile material for future fuel stocks, is a resource that will be needed when economic uranium supplies for the thermal reactors diminish. Further, the fast-fission fuel cycle in which material is recycled (a basic requirement to meet sustainability criteria) offers the flexibility needed to contribute decisively towards solving the problem of growing “spent” fuel inventories by greatly reducing the volume, the heat load and the radiotoxic inventory of high-level wastes that must be disposed of in long-term geological repositories. This is a waste management option that will play an increasingly important role in the future, and help to ensure that nuclear energy remains a sustainable long-term option in the world’s overall energy mix. In recognition of the fast reactor’s importance for the sustainability of the nuclear option, currently there is worldwide renewed interest in fast reactor technology development, as indicated, e.g., by the outcome of the Generation IV International Forum (GIF) technology review, which concluded with 3 out of 6 innovative systems to be fast reactors (gas cooled fast reactor, sodium cooled fast reactor, and heavy liquid metal cooled fast reactor), plus a potential fast core for a 4th concept, the super-critical water reactor. Currently, fast reactor construction projects are ongoing in India (PFBR) and Russian Federation (BN-800), whilst in China the first experimental fast reactor (CEFR) is in the commissioning phase. Fast reactor programs are also carried out in Europe (in particular in France), Japan, Republic of Korea and the USA. The most important challenges for fast reactors are in the areas of cost competitiveness with respect to LWRs and other energy sources, enhanced safety, non-proliferation, and public acceptance. With the exception of this latter, these translate into technology development challenges, i.e. the development of advanced reactor

  10. Technical Meeting on Passive Shutdown Systems for Liquid Metal-Cooled Fast Reactors. Working Material

    International Nuclear Information System (INIS)

    2015-01-01

    A major focus of the design of modern fast reactor systems is on inherent and passive safety. Specific systems to improve reactor safety performance during accidental transients have been developed in nearly all fast reactor programs, and a large number of proposed systems have reached various stages of maturity. This Technical Meeting on Passive Shutdown Systems for Fast Reactors, which was recommended by the Technical Working Group on Fast Reactors (TWG-FR), addressed Member States’ expressed need for information exchange on projects and programs in the field, as well as for the identification of priorities based on the analysis of technology gaps to be covered through R&D activities. This meeting was limited to shutdown systems only, and did not include other passive features such as natural circulation decay heat removal systems etc.; however the meeting catered to passive shutdown safety devices applicable to all types of fast neutron systems. It was agreed to initiate a new study and produce a Nuclear Energy Series (NES) Technical Report to collect information about the existing operational systems as well as innovative concepts under development. This will be a useful source for member states interested in gaining technical expertise to develop passive shutdown systems as well as to highlight the importance and development in this area

  11. HFBR: Review of the technical specifications against the FSAR

    International Nuclear Information System (INIS)

    Rao, D.V.; Boss, S.B.; Claiborne, E.R.; Darby, J.L.; Clark, R.A.

    1990-01-01

    The purpose of this review is to determine the adequacy of the High Flux Beam Reactor (HFBR) Technical Specifications for 40 MW operation by comparison with the HFBR Final Safety Analysis Report, particularly the accident analyses chapter. Specifically, the Technical Specifications were compared against the Design Basis Accident (DBA) Analyses presented in the Addendum to the HFBR FSAR for 60 MW Operation. The 60 MW DBA analyses was used since it is more current and complete than the analyses presented in the original FSAR which is considered obsolete. A listing of the required systems and equipment was made for each of the accidents analyzed. Additionally, the Technical Specification instrument setpoints were compared to the DBA analyses parametric values. Also included in this review was a comparison of the Technical Specification Bases against the FSAR and the identification of any differences. The HFBR Operations Procedures Manual (OPM) was also reviewed for any inconsistencies between the FSAR or the Technical Specifications. Upon completion of this review it was determined that the Technical Specifications are well written and the items commented on should not delay the low power restart (40 MW). Additionally, the OPM is also well written and does not require further modification before restart

  12. Independent Technical (open-quotes Red Teamclose quotes) Reviews

    International Nuclear Information System (INIS)

    Thullen, P.; Bennett, D.R.; Kosiewicz, S.T.; Weaver, D.L.

    1995-01-01

    Offices under the Assistant Secretary for Environmental Restoration and Waste Management (EM) in the Department of Energy (DOE) and some National Laboratories are using Independent Technical or open-quotes Red Teamclose quotes Reviews to understand and improve the performance of major projects, major system acquisitions, programs and organizations. A core group formed in 1991 by Los Alamos National Laboratory and Sandia National Laboratories, has organized teams of commercial and private consultants to perform over fifteen Independent Technical Reviews (ITRs) throughout the DOE Complex. This paper discusses: review initiation, team formation, methodology, site response, and observations gathered over the past three years

  13. Gas-cooled reactor technology safety and siting. Report of a technical committee meeting. Working material

    International Nuclear Information System (INIS)

    1990-01-01

    At the invitation of the Government of the Union of Soviet Socialist Republics, the Eleventh International Conference on the HTGR and the IAEA Technical Committee Meeting on Gas-Cooled Reactor Technology, Safety and Siting were held in Dimitrovgrad, USSR, on June 21-23, 1989. The Technical Committee Meeting provided the Soviet delegates with an opportunity to display the breadth of their program on HTGRs to an international audience. Nearly one-half of the papers were presented by Soviet participants. Among the highlights of the meeting were the following: the diverse nature and large magnitude of the Soviet research and development program on high temperature gas-cooled reactors; the Government approval of the budget for the construction of the 30 MWt High Temperature Test Reactor (HTTR) in Japan (The schedule contemplates a start of construction in spring 1990 on a site at the Oarai Research Establishment and about a five year construction period.); disappointment in the announced plans to shutdown both the Fort St. Vrain (FSV) plant in the United States (US) and the Thorium High Temperature Reactor (THTR-300) in Germany (These two reactors presently represent the only operating HTGRs in the world since the AVR plant in Juelich, Germany, was also shutdown at the end of 1988.); the continuing negotiations between Germany and the USSR on the terms of the co-operation between the two countries for the construction of a HTR Module supplemented by joint research and development activities aimed at increasing coolant outlet temperatures from 750 deg. C to 950 deg. C; the continued enthusiasm displayed by both the US and German representatives for the potential of the small modular designs under development in both countries and the ability for these designs to meet the stringent requirements demanded for the future expansion of nuclear power; the combining of the HTGR technology interest of ABB-Atom and Siemens in Germany into a joint enterprise, HTR GmbH, in May 1989

  14. Proceedings of the 6th IAEA Technical Committee meeting on energetic particles in magnetic confinement systems

    International Nuclear Information System (INIS)

    2000-03-01

    The sixth IAEA Technical Committee Meeting was organized by Japan Atomic Energy Research Institute. It was held at Naka, JAERI during October 12-14, 1999. The previous meetings of this series, formerly entitled 'Alpha Particles in Fusion Research', were held biennially in Kiev (1989), Aspenas (1991), Trieste (1993), Princeton (1995), and Abingdon (1997). The scope of the meeting covered theoretical and experimental work on alpha particle physics, transport of energetic particles, effects of energetic particles on fusion plasma, related collective phenomena, runaway electrons in disruption and diagnostics on energetic particles. The TCM was attended by over 60 participants. Twenty seven papers were presented orally and 19 papers as posters. This proceedings include 37 contributed papers in the meeting. (J.P.N.)

  15. Use of PSA Level 2 analysis for improving containment performance. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1998-03-01

    In order to discuss and exchange experience on different aspects of methods associated with Level 2 PSA and its applications for improving containment performance, the IAEA held a Technical Committee meeting in Vienna in December 1996. The meeting, which was attended by 26 participants from 20 Member States, provided a broad forum for discussion. The meeting addressed the issues related to the actual performance of Level 2 PSA studies as well as the insights gained from applications to improve containment performance. Particular attention was given to studies and applications for WWER type reactors, for which Level 2 work is still in its early stages, and for channel type reactors where modelling of accident progression is complex and significantly different from vessel type light water reactors. This TECDOC contains the papers presented at the meeting and the results of extensive discussions which were held in specific working groups

  16. Proceedings of the 6th IAEA Technical Committee meeting on energetic particles in magnetic confinement systems

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    The sixth IAEA Technical Committee Meeting was organized by Japan Atomic Energy Research Institute. It was held at Naka, JAERI during October 12-14, 1999. The previous meetings of this series, formerly entitled 'Alpha Particles in Fusion Research', were held biennially in Kiev (1989), Aspenas (1991), Trieste (1993), Princeton (1995), and Abingdon (1997). The scope of the meeting covered theoretical and experimental work on alpha particle physics, transport of energetic particles, effects of energetic particles on fusion plasma, related collective phenomena, runaway electrons in disruption and diagnostics on energetic particles. The TCM was attended by over 60 participants. Twenty seven papers were presented orally and 19 papers as posters. This proceedings include 37 contributed papers in the meeting. (J.P.N.)

  17. Control assembly materials for water reactors: Experience, performance and perspectives. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2000-02-01

    The safe, reliable and economic operation of water cooled nuclear power reactors depends to a large extent upon the reliable operation of control assemblies for the regulation and shutdown of the reactors. These consist of neutron absorbing materials clad in stainless steel or zirconium based alloys, guide tubes and guide cards, and other structural components. Current designs have worked extremely well in normal conditions, but less than ideal behaviour limits the lifetimes of control materials, imposing an economic penalty which acts as a strong incentive to produce improved materials and designs that are more reliable. Neutron absorbing materials currently in use include the ceramic boron carbide, the high melting point metal hafnium and the low melting point complex alloy Ag-In-Cd. Other promising neutron absorbing materials, such as dysprosium titanate, are being evaluated in the Russian Federation. These control materials exhibit widely differing mechanical, physical and chemical properties, which must be understood in order to be able to predict the behaviour of control rod assemblies. Identification of existing failure mechanisms, end of life criteria and the implications of the gradual introduction of extended burnup, mixed oxide (MOX) fuels and more complex fuel cycles constitutes the first step in a search for improved materials and designs. In the early part of this decade, it was recognized by the International Working Group on Fuel Performance and Technology (IWGFPT) that international conferences, symposia and published reviews on the materials science aspects of control assemblies were few and far between. Consequently, the IWGFPT recommended that the IAEA should rectify this situation with a series of Technical Committee meetings (TCMs) devoted entirely to the materials aspects of reactor control assemblies. The first was held in 1993 and in the intervening five years considerable progress has been made. In bringing together experts in the

  18. Independent Technical Review of the X-740 Groundwater Remedy, Portsmouth, Ohio: Technical Evaluation and Recommendations

    International Nuclear Information System (INIS)

    Looney, B.; Rhia, B.; Jackson, D.; Eddy-Dilek, C.

    2010-01-01

    Environmental Management (EM-32) to provide an independent technical panel to review previous and ongoing remedial activities designed to address TCE contamination in groundwater at X-740. In 1999, a corrective action was implemented at X-740 to address contamination in the groundwater. The DOE planted poplar trees over 2.6 acres of the groundwater plume. After several years of groundwater monitoring, the results indicated that the benefits of phytoremediation were limited and insufficient to meet remedial objectives. In 2007, an alternative remedial strategy based on in situ oxidative treatment was negotiated with Ohio EPA. During FY2008, three treatment phases of chemical oxidation were completed. The general charter for the independent technical review team is to review the results of s previous and ongoing remedial actions to determine whether the current strategy will be effective in meeting the end points specified in the regulatory work plan.

  19. Independent Technical Review of the X-740 Groundwater Remedy, Portsmouth, Ohio: Technical Evaluation and Recommendations

    Energy Technology Data Exchange (ETDEWEB)

    Looney, B.; Rhia, B.; Jackson, D.; Eddy-Dilek, C.

    2010-04-30

    Energy Office of Environmental Management (EM-32) to provide an independent technical panel to review previous and ongoing remedial activities designed to address TCE contamination in groundwater at X-740. In 1999, a corrective action was implemented at X-740 to address contamination in the groundwater. The DOE planted poplar trees over 2.6 acres of the groundwater plume. After several years of groundwater monitoring, the results indicated that the benefits of phytoremediation were limited and insufficient to meet remedial objectives. In 2007, an alternative remedial strategy based on in situ oxidative treatment was negotiated with Ohio EPA. During FY2008, three treatment phases of chemical oxidation were completed. The general charter for the independent technical review team is to review the results of s previous and ongoing remedial actions to determine whether the current strategy will be effective in meeting the end points specified in the regulatory work plan.

  20. 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)

  1. Report on the IAEA technical meeting on database of evaluated cross sections for ion beam applications

    International Nuclear Information System (INIS)

    Vickridge, I.C.; Schwerer, O.

    2003-11-01

    Results of the IAEA Technical Meeting on Database of Evaluated Cross Sections for Ion Beam Applications held at the IAEA Headquarters, Vienna, Austria, 29 to 30 October 2003, are summarized in this report. The meeting discussed the nuclear data needs for ion beam analysis and produced recommendations concerning the compilation, assessment and evaluation of cross section data for ion beam analysis, as well as the related databases and their formats and their inclusion in the data collections of the IAEA Nuclear Data Section. (author)

  2. High Burnup Fuel: Implications and Operational Experience. Proceedings of a Technical Meeting

    International Nuclear Information System (INIS)

    2016-08-01

    This publication reports on the outcome of a technical meeting on high burnup fuel experience and economics, held in Buenos Aires, Argentina in 2013. The purpose of the meeting was to revisit and update the current operational experience and economic conditions associated with high burnup fuel. International experts with significant experience in experimental programmes on high burnup fuel discussed and evaluated physical limitations at pellet, cladding and structural component levels, with a wide focus including fabrication, core behaviour, transport and intermediate storage for most types of commercial nuclear power plants

  3. Paramedics' non-technical skills: a literature review.

    Science.gov (United States)

    Shields, Allan; Flin, Rhona

    2013-05-01

    Healthcare organisations have started to examine the impact that the human worker has on patient safety. Adopting the Crew Resource Management (CRM) approach, used in aviation, the CRM or non-technical skills of anaesthetists, surgeons, scrub practitioners and emergency physicians have recently been identified to assist in their training and assessment. Paramedics are exposed to dynamic and dangerous situations where patients have to be managed, often with life-threatening injuries or illness. As in other safety-critical domains, the technical skills of paramedics are complemented by effective non-technical skills. The aim of this paper was to review the literature on the non-technical (social and cognitive) skills used by paramedics. This review was undertaken as part of a task analysis to identify the non-technical skills used by paramedics. Of the seven papers reviewed, the results have shown very little research on this topic and so reveal a gap in the understanding of paramedic non-technical skills.

  4. Small reactors with simplified design. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-11-01

    There is a potential future need for small reactors for applications such as district heating, electricity production at remote locations and desalination. Nuclear energy can provide an environmentally benign alternative to meet these needs. For successful deployment, small reactors must satisfy the requirements of users, regulators and the general public. The IAEA has been following the developments in the field of small reactors as a part of the sub-programme on advanced reactor technology. In accordance with the interests of Member States, a Technical Committee meeting (TCM) was organized in Mississauga, Ontario, Canada, 15-19 May 1995 to discuss the status of designs and design requirements related to small reactors for diverse applications. The papers presented at the TCM and a summary of the discussions are contained in this TECDOC which, it is hoped, will serve the Member States as a useful source of technical information on the development of small reactors with simplified design

  5. Advanced Small Modular Reactor (SMR) Probabilistic Risk Assessment (PRA) Technical Exchange Meeting

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Curtis [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2013-09-01

    During FY13, the INL developed an advanced SMR PRA framework which has been described in the report Small Modular Reactor (SMR) Probabilistic Risk Assessment (PRA) Detailed Technical Framework Specification, INL/EXT-13-28974 (April 2013). In this framework, the various areas are considered: Probabilistic models to provide information specific to advanced SMRs Representation of specific SMR design issues such as having co-located modules and passive safety features Use of modern open-source and readily available analysis methods Internal and external events resulting in impacts to safety All-hazards considerations Methods to support the identification of design vulnerabilities Mechanistic and probabilistic data needs to support modeling and tools In order to describe this framework more fully and obtain feedback on the proposed approaches, the INL hosted a technical exchange meeting during August 2013. This report describes the outcomes of that meeting.

  6. Meeting

    Indian Academy of Sciences (India)

    1985-11-07

    Nov 7, 1985 ... Business Meeting of Fellows. Evening Lecture. Architecture of the universe- R Cowsik ... and technical capabilities to plan, design and build satellites for earth observations, such as. Bhaskara I and II have ... Water Resources Systems Planning-. Some case studies for India. Edited by. Mahesh C Chaturvedi ...

  7. Commercial products and services of research reactors. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2013-07-01

    Although the number of operational research reactors is steadily decreasing, more than half of those that remain are greatly underutilized and, in most cases, underfunded. To continue to play a key role in the development of peaceful uses of nuclear technology, the remaining research reactors will need to provide useful products and services to private, national and regional customers, in some cases with adequate revenue generation for reliable, safe and secure facility management and operation. In the light of declining governmental financial support and the need for improved physical security and conversion to low enriched uranium (LEU) fuel, many research reactors have been challenged to generate income to offset increasing operational and maintenance costs. The renewed interest in nuclear power (and therefore in nuclear education and training), the global expansion of diagnostic and therapeutic nuclear medicine, and the extensive use of semiconductors in electronics and in other areas have created new opportunities for research reactors, prominent among them, markets for products and services in regions and countries without such facilities. It is clear that such initiatives towards greater self-reliance will need to address such aspects as market surveys, marketing and business plans, and cost of delivery services. It will also be important to better inform present and future potential end users of research reactor services of the capabilities and products that can be provided. This publication is a compilation of material from an IAEA technical meeting on “Commercial Products and Services of Research Reactors”, held in Vienna, Austria, from 28 June to 2 July 2010. The overall objective of the meeting was to exchange information on good practices and to provide concrete examples, in technical presentations and brainstorming discussions, to promote and facilitate the development of commercial applications of research reactors. The meeting also aimed to

  8. 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)

  9. The International Sailing Canoe: A Technical Review

    Science.gov (United States)

    1994-10-01

    belongs to Brit- ish Army Captain John MacGregor. While recuperating from a railway accident in 1865 he designed a small boat for ex- ploring the coasts ...Review,~ COM. poIltn, Vol. 20, No. 4. July 1989. pp. 3 17-328 10 Vang. T. Y , F",.k Ekmtlllt 5trw:tural Al\\O.l)’,u. Prentice·Hall , En· glewood Clif " NJ

  10. Research Reactor Application for Materials under High Neutron Fluence. Proceedings of an IAEA Technical Meeting (TM-34779)

    International Nuclear Information System (INIS)

    2011-05-01

    Research reactors (RRs) have played, and continue to play, a key role in the development of the peaceful uses of nuclear energy and technology. The role of the IAEA is to assist Member States in the effective utilization of these technologies in various domains of research such as fundamental and applied science, industry, human health care and environmental studies, as well as nuclear energy applications. In particular, material testing reactors (MTRs), serve as unique tools in scientific and technological development and they have quite a wide variety of applications. Today, a large range of different RR designs exist when compared with power reactors and they also have different operating modes, producing high neutron fluxes, which may be steady or pulsed. Recently, an urgent need has arisen for the development of new advanced materials, for example in the nuclear industry, where RRs offer capacities for irradiation programmes. Besides the scientific and research activities and commercial applications, RRs are also used extensively for educational training activities for scientists and engineers. This report is a compilation of outputs of an IAEA Technical Meeting (TM-34779) held on Research Reactor Application for Materials under High Neutron Fluence. The overall objective of the meeting was to review typical applications of small and medium size RRs, such as material characterization and testing, neutron physics and beam research, neutron radiography and imaging as well as isotope production and other types of non-nuclear applications. Several issues were discussed during the meeting, in particular: (1) recent development of irradiation facilities, specific irradiation programmes and their implementation; (2) effective and optimal RR operation regimes for irradiation purposes; (3) sharing of best practices and existing technical knowledge; and (4) fostering of advanced or innovative technologies, e.g. information exchange and effective collaboration. This

  11. A Study of Technical Engineering Peer Reviews at NASA

    Science.gov (United States)

    Chao, Lawrence P.; Tumer, Irem Y.; Bell, David G.

    2003-01-01

    This report describes the state of practices of design reviews at NASA and research into what can be done to improve peer review practices. There are many types of reviews at NASA: required and not, formalized and informal, programmatic and technical. Standing project formal reviews such as the Preliminary Design Review and Critical Design Review are a required part of every project and mission development. However, the technical, engineering peer reviews that support teams' work on such projects are informal, some times ad hoc, and inconsistent across the organization. The goal of this work is to identify best practices and lessons learned from NASA's experience, supported by academic research and methodologies to ultimately improve the process. This research has determined that the organization, composition, scope, and approach of the reviews impact their success. Failure Modes and Effects Analysis (FMEA) can identify key areas of concern before or in the reviews. Product definition tools like the Project Priority Matrix, engineering-focused Customer Value Chain Analysis (CVCA), and project or system-based Quality Function Deployment (QFD) help prioritize resources in reviews. The use of information technology and structured design methodologies can strengthen the engineering peer review process to help NASA work towards error-proofing the design process.

  12. Report on the IAEA consultants' meeting on the co-ordination of nuclear reaction data centres (technical aspects)

    International Nuclear Information System (INIS)

    Schwerer, O.

    2001-07-01

    This report summarizes the results of the IAEA Consultants' Meeting on the Co-ordination of Nuclear Reaction Data Centres (Technical Aspects), held at the IAEA Headquarters, Vienna, Austria, 28 to 30 May 2001. The meeting was attended by 16 participants from 10 co-operating data centres from six Member States and two International Organizations. The report contains a meeting summary, the conclusions and actions, progress and status reports of the participating data centres and working papers considered at the meeting. (author)

  13. Alcohol Fuels Program technical review, Spring 1984

    Energy Technology Data Exchange (ETDEWEB)

    1984-10-01

    The alcohol fuels program consists of in-house and subcontracted research for the conversion of lignocellulosic biomass into fuel alcohols via thermoconversion and bioconversion technologies. In the thermoconversion area, the SERI gasifier has been operated on a one-ton per day scale and produces a clean, medium-Btu gas that can be used to manufacture methanol with a relatively small gas-water shift reaction requirement. Recent research has produced catalysts that make methanol and a mixture of higher alcohols from the biomass-derived synthetic gas. Three hydrolysis processes have emerged as candidates for more focused research. They are: a high-temperature, dilute-acid, plug-flow approach based on the Dartmouth reactor; steam explosion pretreatment followed by hydrolysis using the RUT-C30 fungal organism; and direct microbial conversion of the cellulose to ethanol using bacteria in a single or mixed culture. Modeling studies, including parametric and sensitivity analyses, have recently been completed. The results of these studies will lead to a better definition of the present state-of-the-art for these processes and provide a framework for establishing the research and process engineering issues that still need resolution. In addition to these modeling studies, economic feasibility studies are being carried out by commercial engineering firms. Their results will supplement and add commercial validity to the program results. The feasibility contractors will provide input at two levels: Technical and economic assessment of the current state-of-the-art in alcohol production from lignocellulosic biomass via thermoconversion to produce methanol and higher alcohol mixtures and bioconversion to produce ethanol; and identification of research areas having the potential to significantly reduce the cost of production of alcohols.

  14. Implementation of burnup credit in spent fuel management systems. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2001-08-01

    The purpose of this Technical Committee Meeting was to explore the status of international activities related to the use of burnup credit for spent fuel applications. This was the second major meeting on the issues of burnup credit for spent fuel management systems held since the IAEA began to monitor the uses of burnup credit in spent fuel management systems in 1997. Burnup credit for wet and dry storage systems is needed in many Member States to allow for increased initial fuel enrichment, and to increase the storage capacity and thus to avoid the need for extensive modifications of the spent fuel management systems involved. This document contains 31 individual papers presented at the Meeting; each of the papers was indexed separately

  15. Behaviour of LWR core materials under accident conditions. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1996-12-01

    At the invitation of the Government of the Russian Federation, following a proposal of the International Working Group on Water Reactor Fuel Performance and Technology, the IAEA convened a Technical Committee Meeting on Behaviour of LWR Core Materials Under Accident Conditions from 9 to 13 October 1995 in Dimitrovgrad to analyze and evaluate the behaviour of LWR core materials under accident conditions with special emphasis on severe accidents. In-vessel severe accidents phenomena were considered in detail, but specialized thermal hydraulic aspects as well as ex-vessel phenomena were outside the scope of the meeting. Forty participants representing eight countries attended the meeting. Twenty-three papers were presented and discussed during five sessions. Refs, figs, tabs

  16. Safety related design and economic aspects of HTGRs. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2001-04-01

    The purpose of the Technical Committee Meeting (TCM) was to provide the opportunity to review the status of design and development activities associated with safety related and economic aspects of HTGRs, and to identify pathways which may provide the opportunity for international cooperation in addressing these issues. The HTGR, as a nuclear heat source for the safe, economic and efficient production of electricity and high temperature industrial processes has, within the past few years, become a significantly increasing influence in the future of nuclear power. Nuclear test facilities with the capability of achieving core outlet temperatures to 950 deg. C are presently under construction in China and Japan. These plants will be utilized to support HTGR research and development activities, including electricity generation via the gas turbine and validation of high temperature process heat applications. Also, major development programmes focusing on the generation of electricity through the direct cycle gas turbine are in progress by ESKOM, the state electric utility of South Africa, and by a consortium of organizations from the Russian Federation, USA, France and Japan. Other national programmes focusing on research and development of the HTGR are underway including the Netherlands, where an evaluation is being completed on a heat and power co-generation plant utilizing a small direct cycle HTR; in Germany, where the primary focus is centered on basic issues of reactor safety and innovative reactor technology; in Indonesia with the evaluation of process heat applications such as coal liquefaction, hydrogen production and high temperature reforming of methane; and in the USA with the recent re-introduction of national support for the HTGR specifically directed to the burning of weapons plutonium. The status information presented in several of the papers is as of the time of drafting. Thus other later material should be referenced for more current status information

  17. Advanced Fuel Pellet Materials and Fuel Rod Design for Water Cooled Reactors. Proceedings of a Technical Committee Meeting

    International Nuclear Information System (INIS)

    2010-10-01

    The economics of current nuclear power plants have improved through increased fuel burnup and longer fuel cycles, i.e. increasing the effective time that fuel remains in the reactor core and the amount of energy it generates. Efficient consumption of fissile material in the fuel element before it is discharged from the reactor means that less fuel is required over the reactor's life cycle, which results in lower amounts of fresh fuel, lower spent fuel storage costs, and less waste for ultimate disposal. Better utilization of fissile nuclear materials, as well as more flexible power manoeuvring, place challenging operational demands on materials used in reactor components, and first of all, on fuel and cladding materials. It entails increased attention to measures ensuring desired in-pile fuel performance parameters that require adequate improvements in fuel material properties and fuel rod designs. These are the main reasons that motivated the IAEA Technical Working Group on Fuel Performance and Technology (TWG-FPT) to recommend the organization of a Technical Committee Meeting on Advanced Fuel Pellet Materials and Fuel Rod Designs for Power Reactors. The proposal was supported by the IAEA TWGs on Advanced Technologies for Light and Heavy Water-Cooled Reactors (TWG-LWR and TWG-HWR), and the meeting was held at the invitation of the Government of Switzerland at the Paul Scherrer Institute in Villigen, from 23 to 26 November 2009. This was the third IAEA meeting on these subjects (the first was held in 1996 in Tokyo, Japan, and the second in 2003 in Brussels, Belgium), which reflects the continuous interest in the above issues among Member States. The purpose of the meeting was to review the current status in the development of fuel pellet materials and to explore recent improvements in fuel rod designs for light and heavy water cooled power reactors. The meeting was attended by 45 specialists representing fuel vendors, nuclear utilities, research and development

  18. Review of technical features in underground laboratories

    Science.gov (United States)

    Ianni, Aldo

    2017-10-01

    Deep underground laboratories are multidisciplinary research infrastructures. The main feature of these laboratories is the reduced cosmic ray muons flux. This characteristic allows searching for rare events such as proton decay, dark matter particles or neutrino interactions. However, biology in extreme environments and geophysics are also studied underground. A number of ancillary facilities are critical to properly operate low background experiments in these laboratories. In this work we review the main characteristics of deep underground laboratories and discuss a few of the low background facilities.

  19. Reviewer agreement in scoring 419 abstracts for scientific orthopedics meetings.

    NARCIS (Netherlands)

    Poolman, R.W.; Keijser, L.C.M.; Waal Malefijt, M.C. de; Blankevoort, L.; Farrokhyar, F.; Bhandari, M.

    2007-01-01

    BACKGROUND: The selection of presentations at orthopedic meetings is an important process. If the peer reviewers do not consistently agree on the quality score, the review process is arbitrary and open to bias. The aim of this study was: (1) to describe the inter-reviewer agreement of a previously

  20. Reviewer agreement in scoring 419 abstracts for scientific orthopedics meetings

    NARCIS (Netherlands)

    Poolman, Rudolf W.; Keijser, Lucien C. M.; de Waal Malefijt, Maarten C.; Blankevoort, Leendert; Farrokhyar, Forough; Bhandari, Mohit

    2007-01-01

    The selection of presentations at orthopedic meetings is an important process. If the peer reviewers do not consistently agree on the quality score, the review process is arbitrary and open to bias. The aim of this study was: (1) to describe the inter-reviewer agreement of a previously designed

  1. Technical Communication: Perspectives for the Eighties, Part 1. Proceedings of the Technical Communications Sessions at the 32Nd Annual Meeting of the Conference on College Composition and Communication

    Science.gov (United States)

    Mathes, J. C. (Compiler); Pinelli, T. E. (Compiler)

    1981-01-01

    Proceeding of the technical communication sessions at the 32nd annual meeting of the Conference on College Composition and Communication held in Dallas, Texas, March 26-28, 1981 are summarized. The proceeding suggest that technical communication has become an important subfield and is becoming an intrinsic part of many undergraduate curricula. Technical communication as a separate discipline, however, is relatively new. For that reason, proceedings that can make current research available as quickly as possible are suggested for preparation. The following topics were addressed: (1) a history and definition of technical writing, (2) the case method is technical communication (3) teaching technical writing (4) oral communication and rhetorical theory, and (5) new approaches in and practical applications of technical writing.

  2. Proceedings of the fuels technology contractors review meeting

    Energy Technology Data Exchange (ETDEWEB)

    Malone, R.D. [ed.

    1993-11-01

    The Fuels Technology Contractors Review Meeting was held November 16-18, 1993, at the Morgantown Energy Technology Center (METC) in Morgantown, West Virginia. This meeting was sponsored and hosted by METC, the Office of Fossil Energy, U.S. Department of Energy (DOE). METC periodically provides an opportunity to bring together all of the R&D participants in a DOE-sponsored contractors review meeting to present key results of their research and to provide technology transfer to the active research community and to the interested public. This meeting was previously called the Natural Gas Technology Contractors Review Meeting. This year it was expanded to include DOE-sponsored research on oil shale and tar sands and so was retitled the Fuels Technology Contractors Review Meeting. Current research activities include efforts in both natural gas and liquid fuels. The natural gas portion of the meeting included discussions of results summarizing work being conducted in fracture systems, both natural and induced; drilling, completion, and stimulation research; resource characterization; delivery and storage; gas to liquids research; and environmental issues. The meeting also included project and technology summaries on research in oil shale, tar sands, and mild coal gasification, and summaries of work in natural-gas fuel cells and natural-gas turbines. The format included oral and poster session presentations. Individual papers have been processed separately for inclusion in the Energy Science and Technology database.

  3. Design measures for prevention and mitigation of severe accidents at advanced water cooled reactors. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1998-06-01

    Over 8500 reactor-years of operating experience have been accumulated with the current nuclear energy systems. New generations of nuclear power plants are being developed, building upon this background of experience. During the last decade, requirements for equipment specifically intended to minimize releases of radioactive material to the environment in the event of a core melt accident have been introduced, and designs for new plants include measures for preventing and mitigating a range of severe accident scenarios. The IAEA Technical Committee Meeting on Impact of Severe Accidents on Plant Design and Layout of Advanced Water Cooled Reactors was jointly organized by the Department of Nuclear Energy and the Department of Nuclear Safety to review measures which are being incorporated into advanced water cooled reactor designs for preventing and mitigating severe accidents, the status of experimental and analytical investigations of severe accident phenomena and challenges which support design decisions and accident management procedures, and to understand the impact of explicitly addressing severe accidents on the cost of nuclear power plants. This publication is intended to provide an objective source of information on this topic. It includes 14 papers presented at the Technical Committee meeting held in Vienna between 21-25 October 1996. It also includes a Summary and Findings of the Working Groups. The papers were grouped in three sections. A separate abstract was prepared for each paper

  4. Technical review of Molten Salt Oxidation

    International Nuclear Information System (INIS)

    1993-12-01

    The process was reviewed for destruction of mixed low-level radioactive waste. Results: extensive development work and scaleup has been documented on coal gasification and hazardous waste which forms a strong experience base for this MSO process; it is clearly applicable to DOE wastes such as organic liquids and low-ash wastes. It also has potential for processing difficult-to-treat wastes such as nuclear grade graphite and TBP, and it may be suitable for other problem waste streams such as sodium metal. MSO operating systems may be constructed in relatively small units for small quantity generators. Public perceptions could be favorable if acceptable performance data are presented fairly; MSO will likely require compliance with regulations for incineration. Use of MSO for offgas treatment may be complicated by salt carryover. Figs, tabs, refs

  5. Acoustic emission: technical review for PWR applications

    International Nuclear Information System (INIS)

    Bentley, P.G.

    1981-07-01

    Acoustic emission has been studied since the early 1960's, particularly with a view to periodic or continuous monitoring of steel pressure vessels. In the years 1970-75 it was realised that ductile steels, used in nuclear vessels, give small amplitude signals which are barely detectable by available instruments. The technique for application in periodic or continuous monitoring and also as applied to leak detection and weld fabrication monitoring is reviewed. It is concluded that manufacturing defects may be detectable during pre-service hydrotest, but that there is insufficient evidence on which to base an estimate of detection probability. In-service hydrotest or continuous monitoring is unlikely to detect growing cracks because of the quiet nature of the material and the noisy reactor background. Both leak detection and fabrication weld monitoring show some promise of successful application in the future. (author)

  6. Forty-Fifth Annual Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

    International Nuclear Information System (INIS)

    2012-01-01

    The objectives of the meeting were to: • Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); • Review the progress since the 44 th TWG-FR Annual Meeting, including the status of the actions; • Consider topical technical meeting arrangements for 2012-2013, as well as review FR-related activities included in the IAEA Programme & Budget (P&B) biennium 2012-2013; • Review the IAEA’s concluded, on-going and planned coordinated research projects in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives (GIF, INPRO, NEA, ESNII, etc.). The 45th Meeting of the TWG-FR reached the following conclusions/recommendations: • The participants expressed satisfaction and appreciation for the large amount of new information on on-going activities carried out by the Member States in the field of FR and ADS exchanged during the meeting; • Also the organizations which have participated to the TWG-FR meeting for the first time expressed their appreciation for the lively discussion and the results and thanked the IAEA for inviting them at the meeting; • The meeting was very useful in particular for collecting inputs and advice in view of the preparation of the IAEA Programme & Budget 2014-2015 (and then 2016-2017) in the area of FR and ADS technology development; • The TWG-FR remains an unique international forum for information exchange in the field of fast neutron systems and for promoting RT&D activities in this area; • Due to the increasing interest in FR and in view of the forthcoming realizations, it would be advisable to increase the involvement of industries, regulators and other R&D organizations; • The annual TWG-FR meeting should focused on exchange of information on national and international programmes, avoiding duplications or overlapping’s with other IAEA initiatives in the field;

  7. Advanced fuels with reduced actinide generation. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1996-11-01

    Nuclear energy can play an important future role in supplying the world population with energy. However, this form of energy will be successful only under certain conditions: it must meet very strict safety requirements, it must be economically competitive, and it must be acceptable to the public. Nuclear power produces radioactive wastes and in several countries the public raises concern about safety. Much development work on advanced nuclear power systems is going on in several countries, with participation of both governmental and private industries to meet these conditions. In the framework of this IAEA activity the Technical Committee Meeting on Advanced Fuels with Reduced Actinide Generation was organized. The aim of the meeting was to highlight current research activities and to identify new research areas and fields of possible co-operation. The scope of the meeting included advanced fuels for all types of nuclear reactors: light water reactors, heavy water reactors, high temperature reactors, fast reactors, molten salt reactors and for accelerator driven systems. Other topics covered a wide range of investigations made, or to be made in the Member States. Refs, figs, tabs

  8. Technical minutes of the eighth INDC meeting, Vienna, 6 - 10 October 1975

    International Nuclear Information System (INIS)

    Benzi, V.

    1977-01-01

    Neutron nuclear data (report on 11th four centre meeting; additional information from neutron data centres other than NDS; two years publication cycle of CINDA; international exchange and assessment of use of evaluated data); non-neutron nuclear data (progress reports on activities, services and coordination of ''non-neutron'' nuclear data centres and groups; report on meeting on charged particle nuclear data (CPND) for applications; discussion on recommendations from ''non-neutron'' nuclear data meetings April/May 1974, including plans for 1976 meetings); coordination of nuclear data activities (status of development of regional nuclear data centres and national data committees; neutron data for reactor dosimetry; FPND newsletter; WRENDA for fission, fusion and safeguards; nuclear data measurements in developing countries; status and NDS targets and samples program); progress reports on nuclear data measurements, facilities and evaluations (additions to submitted progress reports; reports on nuclear data activities in countries not represented on INDC); reports of Technical and Ad-hoc sub-committees; reports of policy sub-committees; meetings

  9. In-Pile Testing and Instrumentation for Development of Generation-IV Fuels and Materials. Proceedings of a Technical Meeting

    International Nuclear Information System (INIS)

    2013-12-01

    For many years, the increase in efficiency in the production of nuclear electricity has been an economic challenge in many countries which have developed this kind of energy. The increase in fuel burnup and fuel residence time leads to a reduction in the volume of fresh fuel loaded and spent fuel discharged, respectively. More demanding nuclear fuel cycle parameters are combined with a need to operate nuclear power plants with maximal availability and load factors, in load-follow mode and with longer fuel cycles. In meeting these requirements, fuel has to operate in a demanding environment of high radiation fields, high temperatures, high mechanical stresses and high coolant flow. Requirements of increased fuel reliability and minimal fuel failures also remain in force. Under such circumstances, continuous development of more radiation resistant fuel materials, especially advanced cladding, careful and incremental examinations, and improved understanding and modelling of high burnup fuel behaviour are required. Following a recommendation of the IAEA Technical Working Group on Fuel Performance and Technology, the Technical Meeting on In-pile Testing and Instrumentation for Development of Generation-IV Fuels and Materials was held in Halden, Norway, on 21-24 August 2012. The purpose of the meeting was to review the current status and the progress in methods and technologies used for the in-pile testing of nuclear fuel achieved since the previous IAEA meeting on In-core Instrumentation and Reactor Core Assessment, also held in Halden in 2007. Emphasis was placed on advanced techniques applied for the understanding of high burnup fuel behaviour of water cooled power reactors that represent the vast majority of the current nuclear reactor fleet. However, the meeting also included papers and discussion on testing techniques applied or developed specifically for new fuel and structural materials considered for Generation-IV systems. The meeting was attended by 43

  10. 77 FR 12354 - Meeting of the Joint Forum on Environmental Technical Cooperation Pursuant to the United States...

    Science.gov (United States)

    2012-02-29

    ... development and effective implementation of Jordanian environmental laws, as defined in Articles 5.4 and 18.2... Cooperation Pursuant to the United States-Jordan Joint Statement on Environmental Technical Cooperation ACTION: Notice of the meeting of the Joint Forum on Environmental Technical Cooperation and request for comments...

  11. Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics. Presentations

    International Nuclear Information System (INIS)

    2013-01-01

    The objectives of the meeting were: • To identify the main issues and technical features that affect capital and energy production costs of fast reactors and related fuel cycle facilities; • To present fast reactor concepts and designs with enhanced economic characteristics, as well as innovative technical solutions (components, subsystems, etc.) that have the potential to reduce the capital costs of fast reactors and related fuel cycle facilities; • To present energy models and advanced tools for the cost assessment of innovative fast reactors and associated nuclear fuel cycles; • To discuss the results of studies and ongoing R&D activities that address cost reduction and the future economic competitiveness of fast reactors; • To identify research and technology development needs in the field, also in view of new IAEA initiatives to help and support Member States in improving the economic competitiveness of fast reactors and associated nuclear fuel cycles

  12. Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics. Working Material

    International Nuclear Information System (INIS)

    2013-01-01

    The objectives of the meeting were: - To identify the main issues and technical features that affect capital and energy production costs of fast reactors and related fuel cycle facilities; - To present fast reactor concepts and designs with enhanced economic characteristics, as well as innovative technical solutions (components, subsystems, etc.) that have the potential to reduce the capital costs of fast reactors and related fuel cycle facilities; - To present energy models and advanced tools for the cost assessment of innovative fast reactors and associated nuclear fuel cycles; - To discuss the results of studies and on-going R&D activities that address cost reduction and the future economic competitiveness of fast reactors; and - To identify research and technology development needs in the field, also in view of new IAEA initiatives to help and support Member States in improving the economic competitiveness of fast reactors and associated nuclear fuel cycles

  13. Design, Manufacturing and Irradiation Behaviour of Fast Reactor Fuel. Proceedings of a Technical Meeting

    International Nuclear Information System (INIS)

    2013-04-01

    Fast reactors are vital for ensuring the sustainability of nuclear energy in the long term. They offer vastly more efficient use of uranium resources and the ability to burn actinides, which are otherwise the long-lived component of high level nuclear waste. These reactors require development, qualification, testing and deployment of improved and innovative nuclear fuel and structural materials having very high radiation resistance, corrosion/erosion and other key operational properties. Several IAEA Member States have made efforts to advance the design and manufacture of technologies of fast reactor fuels, as well as to investigate their irradiation behaviour. Due to the acute shortage of fast neutron testing and post-irradiation examination facilities and the insufficient understanding of high dose radiation effects, there is a need for international exchange of knowledge and experience, generation of currently missing basic data, identification of relevant mechanisms of materials degradation and development of appropriate models. Considering the important role of nuclear fuels in fast reactor operation, the IAEA Technical Working Group on Fuel Performance and Technology (TWGFPT) proposed a Technical Meeting (TM) on 'Design, Manufacturing and Irradiation Behaviour of Fast Reactors Fuels', which was hosted by the Institute of Physics and Power Engineering (IPPE) in Obninsk, Russian Federation, from 30 May to 3 June 2011. The TM included a technical visit to the fuel production plant MSZ in Elektrostal. The purpose of the meeting was to provide a forum to share knowledge, practical experience and information on the improvement and innovation of fuels for fast reactors through scientific presentations and brainstorming discussions. The meeting brought together 34 specialists from national nuclear agencies, R and D and design institutes, fuel vendors and utilities from 10 countries. The presentations were structured into four sections: R and D Programmes on FR Fuel

  14. Report of the first meeting of the Project Advisory Committee (Technical) 21-24 March 1983, at NEMROCK, Cairo

    International Nuclear Information System (INIS)

    Taylor, C.B.G.

    1983-05-01

    The Project Advisory Committee (Technical) (PACT) met on 21-24 March 1983, at NEMROCK, Cairo, Egypt, to discuss the joint IAEA/WHO project on Intracavitary Radiation Therapy for Cancer of the Uterus (Egypt/6/004). At this four day meeting the committee (1) identified a well-defined administrative framework in which earlier diagnosis of uterine cancer may be organized, on a limited but firm basis. (2) Agreed on the clinical and dosimetric principles to be followed in implementing the project. (3) Decided on the types and quantities of equipment which it will need in its first two years. (4) Developed the outline of the syllabus for the first training course, and fixed its date (three weeks from 83-10-29). (5) Reviewed the costs which will be incurred in carrying through the project and found them to be consistent with the funds available

  15. Report on the consultants' meeting on technical aspects of the co-operation of nuclear reaction data centers

    International Nuclear Information System (INIS)

    Lemmel, H.D.; Schwerer, O.; Wienke, H.

    1995-10-01

    The IAEA Nuclear Data Section convenes in annual intervals coordination meetings of the Network of the Nuclear Reaction Data Center. The present meeting dealt with technical matters of the nuclear data compilation and exchange by means of the jointly operated computerized systems CINDA, EXFOR, ENDF and others. Refs, figs and tabs

  16. Second NASA Technical Interchange Meeting (TIM): Advanced Technology Lifecycle Analysis System (ATLAS) Technology Tool Box (TTB)

    Science.gov (United States)

    ONeil, D. A.; Mankins, J. C.; Christensen, C. B.; Gresham, E. C.

    2005-01-01

    The Advanced Technology Lifecycle Analysis System (ATLAS), a spreadsheet analysis tool suite, applies parametric equations for sizing and lifecycle cost estimation. Performance, operation, and programmatic data used by the equations come from a Technology Tool Box (TTB) database. In this second TTB Technical Interchange Meeting (TIM), technologists, system model developers, and architecture analysts discussed methods for modeling technology decisions in spreadsheet models, identified specific technology parameters, and defined detailed development requirements. This Conference Publication captures the consensus of the discussions and provides narrative explanations of the tool suite, the database, and applications of ATLAS within NASA s changing environment.

  17. IAEA technical meeting on fissile material strategies for sustainable nuclear energy

    International Nuclear Information System (INIS)

    Ganguly, Chaitanyamoy; Koyama, Kazutoshi

    2005-01-01

    A Technical Meeting (TM) on 'Fissile Material Management Strategies for Sustainable Nuclear Energy' was organized by the International Atomic Energy Agency (IAEA) in Vienna from 12 to 15 September 2005. Prior to the TM, three Working Groups (WG) composed of experts from 10 countries prepared Key Issues papers on: 1) Uranium Demand and Supply through 2050; 2) Back-end Fuel Cycle Options; and 3) Sustainable Nuclear Energy beyond 2050: Cross-cutting Issues. Some 36 papers, including 3 key issue papers, were presented during the TM in 3 different sessions. The present paper summarizes the deliberations of the TM. (author)

  18. Floating nuclear energy plants for seawater desalination. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-05-01

    Floating nuclear desalination facilities are one of the alternatives being considered. They may offer a particularly suitable choice for remote locations and small island or coastal communities where the necessary manpower and infrastructure to support desalination plants are not available. In the interest of focusing specific attention on the technology of floating nuclear desalination, the IAEA sponsored a Technical Committee Meeting on Floating Nuclear Plants for Seawater Desalination from 29 to 31 May 1995 in Obninsk, Russian Federation. This publication documents the papers and presentations given by experts from several countries at that meeting. It is hoped that the information contained in this report will be a valuable resource for those interested in nuclear desalination, and that it will stimulate further interest in the potential for floating nuclear desalination facilities. Refs, figs, tabs

  19. Deterministic analysis of operational events in nuclear power plants. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2007-03-01

    Computer codes are being used to analyse operational events in nuclear power plants but until now no special attention has been given to the dissemination of the benefits from these analyses. The IAEA's Incident Reporting System contains more than 3000 reported operational events. Even though deterministic analyses were certainly performed for some of them, only a few reports are supplemented by the results of the computer code analysis. From 23-26 May 2005 a Technical Meeting on Deterministic Analysis of Operational Events in Nuclear Power Plants was organized by the IAEA and held at the International Centre of Croatian Universities in Dubrovnik, Croatia. The objective of the meeting was to provide an international forum for presentations and discussions on how deterministic analysis can be utilized for the evaluation of operational events at nuclear power plants in addition to the traditional root cause evaluation methods

  20. Proceedings of the technical committee meeting on sodium removal and disposal from LMFRs in normal operation and in the framework of decommissioning

    International Nuclear Information System (INIS)

    Latge, C.

    1997-11-01

    This publication summarizes discussions and presented papers from the Technical Committee meeting on sodium removal and disposal from liquid metal fast reactors in normal operation and in the framework of decommissioning, organised by IAEA. The objective of this meeting was to provide a forum to review and exchange information on the international developments in technologies of sodium removal and disposal from liquid metal fast reactor components and systems in operation and maintenance conditions, and in framework of decommissioning. The technical parts of the meeting covered the three major subjects: sodium removal (cleaning) process, decontamination process and bulk disposal of sodium in the framework of decommissioning. These technologies were reviewed with regard to their implementation into current plants to improve operation and maintenance, and to develop an effective decommissioning program. Further, design for future Liquid metal fast reactors were reviewed in the context how they can accommodate today's technologies. The meeting resulted in an effective information exchange with the Member States sharing their needs as well as experiences in the mentioned topics

  1. Recent developments in uranium exploration, production and environmental issues. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2005-09-01

    The uranium industry is in a period of transition. In Europe, the industry is in transition from uranium production to site rehabilitation. The WISMUT project in Germany, which is featured in this publication, is the largest and one of the most advanced rehabilitation projects in the world. By contrast, other countries such as China, India and Argentina are expanding their industries to meet growing uranium demand. Activities in these countries, which are also described in this publication, range from new project licensing to application of new technology to increase productivity and lower costs at existing operations. Changes within the uranium industry are nowhere more evident than in the marketplace, where the price of uranium has more than doubled in the past two years. There is a discussion of the reasons for this price rise and the adequacy of production capacity to meet reactor uranium requirements. Many developing countries are striving for self-sufficiency in their uranium production capabilities. Accordingly, the papers deal with a range of topics including uranium exploration, project licensing, and research directed towards improving uranium production efficiency and costs. European papers emphasize uranium site rehabilitation, reflecting the fact that uranium production has all but ceased in Europe. These papers describe site remediation technology that is being utilized at a variety of sites ranging from tailings ponds to mine water treatment plants. The recent rapid increase in the uranium market price has dominated discussions among uranium producers and users alike. Not surprisingly the price increase was also a much-discussed topic at this Technical Meeting. One paper reviewed the reasons for the rapid price increase and the relationship between market price and uranium supply-demand relationships. Uranium production is likely to become more important to Niger's economy if the recent price increase is sustainable. Accordingly, Niger's uranium

  2. Accident Tolerant Fuel Concepts for Light Water Reactors. Proceedings of a Technical Meeting

    International Nuclear Information System (INIS)

    2016-06-01

    Nuclear fuel is a highly complex material that has been subject to continuous development over the past 40 years and has reached a stage where it can be safely and reliably irradiated up to 65 GWd/tU in commercial nuclear reactors. During this time, there have been many improvements to the original designs and materials used. However, the basic design of uranium oxide fuel pellets clad with zirconium alloy tubing has remained the fuel choice for the vast majority of commercial nuclear power plants. Severe accidents, such as those at the Three Mile Island and Fukushima Daiichi have shown that under such extreme conditions, nuclear fuel will fail and the high temperature reactions between zirconoi alloys and water will lead to the generation of hydrogen, with the potential for explosions to occur, daming the plant further. Recognizing that the current fuel designs are vulnerable to severe accident conditions, tehre is renewed interesst in alternative fuel designs that would be more resistant to fuel failure and hydrogen production. Such new fuel designs will need to be compatible with existing fuel and reactor systems if they are to be utilized in the current reactor fleet and in current new build designs, but there is also the possibility of new designs for new reactor systems. This publication provides a record of the Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, held at Oak Ridge National Laboratories (ORNL), United States of America, 13-16 October 2014, to consider the early stages of research and development into accident tolerant fuel. There were 45 participants from 10 countries taking part in the meeting, with 32 papers organized into 7 sessions, of which 27 are included in this publication. This meeting is part of a wider investigation into such designs, and it is anticipated that further Technical Meetings and research programmes will be undertaken in this field

  3. Funding for the 2ND IAEA technical meeting on fusion data processing, validation and analysis

    Energy Technology Data Exchange (ETDEWEB)

    Greenwald, Martin

    2017-06-02

    The International Atomic Energy Agency (IAEA) will organize the second Technical Meeting on Fusion Da Processing, Validation and Analysis from 30 May to 02 June, 2017, in Cambridge, MA USA. The meeting w be hosted by the MIT Plasma Science and Fusion Center (PSFC). The objective of the meeting is to provide a platform where a set of topics relevant to fusion data processing, validation and analysis are discussed with the view of extrapolation needs to next step fusion devices such as ITER. The validation and analysis of experimental data obtained from diagnostics used to characterize fusion plasmas are crucial for a knowledge based understanding of the physical processes governing the dynamics of these plasmas. The meeting will aim at fostering, in particular, discussions of research and development results that set out or underline trends observed in the current major fusion confinement devices. General information on the IAEA, including its mission and organization, can be found at the IAEA websit Uncertainty quantification (UQ) Model selection, validation, and verification (V&V) Probability theory and statistical analysis Inverse problems & equilibrium reconstru ction Integrated data analysis Real time data analysis Machine learning Signal/image proc essing & pattern recognition Experimental design and synthetic diagnostics Data management

  4. 16. meeting of the IFRC Subcommittee on Atomic and Molecular Data for Fusion. Summary report of an IAEA technical meeting

    International Nuclear Information System (INIS)

    Clark, R.E.H.

    2008-11-01

    The 16th meeting of the Subcommittee on Atomic and Molecular (A and M) Data for Fusion of the International Fusion Research Council was held on 17-18 April 2008, at the IAEA Headquarters in Vienna, Austria. Activities of the Atomic and Molecular Data Unit for the period 2006-2008 were reviewed, and recommendations were made for the 2010-2011 programme and budget cycle. The discussions, conclusions and recommendations of the Subcommittee meeting are briefly described in this report. Specific recommendations of the Subcommittee from this meeting, as well as the report on the activities of the IAEA Atomic and Molecular Data Unit for the period May 2006 - March 2008, are also included. Of specific concern is the loss of three key personnel early in the upcoming budget cycle, including the A and M Data Unit Head (Dr. R.E.H. Clark), the Section Head for the Nuclear Data Section (Dr. A.L. Nichols), and the Data Unit coordinator for the computational facilities and databases (Dr. D. Humbert). Timely replacements of these key individuals are critical for the continued effective operation of the Atomic and Molecular Data Unit. (author)

  5. Report on the consultants' meeting on co-ordination of the nuclear reaction data centres. (Technical aspects)

    International Nuclear Information System (INIS)

    Schwerer, O.; Lammer, M.; Pronyaev, V.G.

    1999-08-01

    This report summarizes the 1999 Co-ordination Meeting on Technical Aspects of the Co-operation of the Nuclear Reaction Data Centres, hold at the IAEA Headquarters in Vienna, Austria, 18 to 20 May 1999. The meeting was attended by scientists from 11 Nuclear Data Centres from 7 Member States and 2 International Organizations. The present document contains a meeting summary, the conclusions and actions, and progress reports of the Participating Data Centres. (author)

  6. Report on the consultants' meeting on co-ordination of the nuclear reaction data centers (technical aspects)

    International Nuclear Information System (INIS)

    Schwerer, O.; Wienke, H.

    1997-10-01

    The report summarizes the co-ordination meeting of the network of Nuclear Reaction Data Centres organized by the IAEA in 1997. The meeting was attended by technical staff from ten member centres of the network (representing USA, Russia, China, Japan, Hungary, OECD-NEA and IAEA) to discuss technical matters of the nuclear data compilation and exchange by means of the jointly operated computerized systems CINDA, EXFOR, ENDF and others. Observers from Belgium and Ukraine also attended the meeting. The document includes status reports of all centres and selected working papers

  7. Report of a Technical Meeting on ''Alpha emitting radionuclides and radiopharmaceuticals for therapy''

    International Nuclear Information System (INIS)

    2013-01-01

    Considering the high potential of α-emitters for future development of radionuclide therapy, the International Atomic Energy Agency (IAEA) organized a Technical Meeting on ‘Alpha Emitting Radionuclides and Radiopharmaceuticals for Therapy’, from June 24 to 28, 2013, at IAEA Headquarters in Vienna with the purpose of gathering eminent Experts in the field and discuss with them the status and future perspectives of the field. Sixteen Experts and two External Observers from ten different countries, and four IAEA Technical Officers attended this meeting. Outstanding lectures have been presented covering all relevant aspects of α-therapy, which were followed by extensive discussions and analysis. Selected arguments encompassed production methods and availability of alpha-emitting radionuclides, labelling chemistry of alpha-emittting radioelements, design and development of target-specific radiopharmaceuticals, physical principles of alpha-particle dosimetry and advanced dosimetric models, biological effects of alpha radiation at the cellular level, on-going preclinical and clinical studies with new radiopharmaceuticals, results of clinical trials on the use of radium-223 chloride solutions for the treatment of metastatic bone cancer. The broad scientific background of invited components of the Experts’ panel conferred a strong interdisciplinary trait to the overall discussion and stimulated a critical analysis of this emerging unexplored field. Results of this comprehensive overview on alpha therapy, including recommendations to the Agency on suitable initiatives that may help to promote and spread the knowledge to Members States on this emerging therapeutic modality, are summarized in the present Report

  8. Integral design concepts of advanced water cooled reactors. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-11-01

    Under the sub-programme on non-electrical applications of advanced reactors, the International Atomic Energy Agency has been providing a worldwide forum for exchange of information on integral reactor concepts. Two Technical Committee meetings were held in 1994 and 1995 on the subject where state-of-the-art developments were presented. Efforts are continuing for the development of advanced nuclear reactors of both evolutionary and innovative design, for electricity, co-generation and heat applications. While single purpose reactors for electricity generation may require small and medium sizes under certain conditions, reactors for heat applications and co-generation would be necessary in the small and medium range and need to be located closer to the load centres. The integral design approach to the development of advanced light water reactors has received special attention over the past few years. Several designs are in the detailed design stage, some are under construction, one prototype is in operation. A need has been felt for guidance on a number of issues, ranging from design objectives to the assessment methodology needed to show how integral designs can meet these objectives, and also to identify their advantages and problem areas. The technical document addresses the current status of the design, safety and operational issues of integral reactors and recommends areas for future development

  9. Organizational factors influencing human performance in nuclear power plants. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-05-01

    In 1991 a Safety Series report on Safety Culture of the International Nuclear Safety Advisory Group (INSAG) was published as 75-INSAG-4 by the IAEA. This report deals with the concept of Safety Culture as it relates to organizations and individuals involved in the operations of nuclear power plants (NPPs). Generally, the role of management and organization in assuring the safe operation of NPPs has been widely recognized and its importance accepted. However, the understanding of what constitutes effective management and organization the area of safety is less developed than the understanding of most of the technical issues which plant operators and regulatory bodies are confronted with. The Technical Committee meeting provided a forum for a broad exchange of information on practices and experiences in the area of organization and management to accomplish operational safety in NPPs and thus enhance Safety Culture. This report and the papers presented at the meeting discuss those factors which influence and improve human performance covering both aspects, i.e. the basic requirements imposed on the operator and the ways of managerial support which enhance the reliable and safety oriented performance of operators. Refs, figs, tabs

  10. Characterization and testing of materials for nuclear reactors. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2007-03-01

    Nuclear techniques in general and neutrons based methods in particular have played and will continue to play an important role in research in materials science and technology. Today the world is looking at nuclear fission and nuclear fusion as the main sources of energy supply for the future. Research reactors have played a key role in the development of nuclear technology. A materials development programme will thus play a major role in the design and development of new nuclear power plants, for the extension of the life of operating reactors as well as for fusion reactors. Against this background, the IAEA had organized a Technical Meeting on Development, Characterization and Testing of Materials - With Special Reference to the Energy Sector under the activity on specific applications of research reactors. The meeting was held in Vienna, May 29- June 2, 2006. There was also participation by experts in techniques, complementary to neutrons. The participants for the technical meeting were experts in the utilization of nuclear techniques namely the high flux and medium flux research reactors, fusion research and positron annihilation. They presented the design, development and utilization of the facilities at their respective centres for materials characterization with main focus on materials for nuclear energy, both fission and fusion. In core irradiation of materials, development of instrument for residual stress measurement in large and / or irradiated specimen, neutron radiography for inspection of irradiated fuel, work on oxide dispersion strengthened (ODS) steels and SiC composites, relevant to future power systems were cited as application of nuclear techniques in fission reactors. The use of neutron scattering for helium bubbles in steel, application of positron annihilation to study helium bubbles in Cu, Ti-stabilized stainless steel and voidswelling studies etc. show that these techniques have an important role in the development of materials for energy

  11. Research reactor instrumentation and control technology. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-10-01

    The majority of research reactors operating today were put into operation 20 years ago, and some of them underwent modifications, upgrading and refurbishing since their construction to meet the requirements for higher neutron fluxes. However, a few of these ageing research reactors are still operating with their original instrumentation and control systems (I and C) which are important for reactor safety to guard against abnormal occurrences and reactor control involving startup, shutdown and power regulation. Worn and obsolete I and C systems cause operational problems as well as difficulties in obtaining replacement parts. In addition, satisfying the stringent safety conditions laid out by the nuclear regulatory bodies requires the modernization of research reactors I and C systems and integration of additional instrumentation units to the reactor. In order to clarify these issues and to provide some guidance to reactor operators on state-of-art technology and future trends for the I and C systems for research reactors, a Technical Committee Meeting on Technology and Trends for Research Reactor Instrumentation and Controls was held in Ljubljana, Slovenia, from 4 to 8 December 1995. This publication summarizes the discussions and recommendations resulting from that meeting. This is expected to benefit the research reactor operators planning I and C improvements. Refs, figs, tabs

  12. CERN Technical Training 2004: New Short Course III (SC III) on Microsoft Outlook - Meetings and Delegation

    CERN Multimedia

    Monique Duval

    2004-01-01

    The CERN Technical Training programme is now proposing a new format for courses on Microsoft Outlook. Three two-hours Short Courses (SC) cover basic and advanced functionalities of the recommended mail client for email at CERN. Each module can be followed independently. The next scheduled session of the 3rd module will take place as follows: Outlook (SC III): Meetings and Delegation. Next session: 9.11.2004 (14:00-16:00) SC III will cover how to organise and manage meetings, work with meeting requests, share tasks, and use email and calendar delegation. The number of participants to each session is limited to 8. The instructor is English-French bilingual, and she will be available some time after each session to answer specific questions, or provide further explanations following demand. The cost of attending any SC module on Outlook is 70.- CHF. The above session will be confirmed if there are enough participants, and the attendance costs will be lower in case of a full class. If you are interested in...

  13. Improving the Database for Physical and Chemical Sputtering. Summary Report of an IAEA Technical Meeting

    International Nuclear Information System (INIS)

    Braams, B. J.

    2013-02-01

    Seven experts and IAEA staff convened in Vienna to review the existing database for physical and chemical sputtering of fusion wall materials and to make recommendations about priorities for further work. Recommendations were made about database needs for pure and mixed Be, C and W wall material for the processes of physical and chemical sputtering, reflection, penetration and trapping and also for effects of surface and material microstructure. The proceedings and recommendations of the meeting are summarized here. (author)

  14. Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics. Working Material

    International Nuclear Information System (INIS)

    2013-01-01

    In recent years, engineering oriented work, rather than basic research and development (R&D), has led to significant progress in improving the economics of innovative fast reactors and associated fuel cycle facilities, while maintaining and even enhancing the safety features of these systems. Optimization of plant size and layout, more compact designs, reduction of the amount of plant materials and the building volumes, higher operating temperatures to attain higher generating efficiencies, improvement of load factor, extended core lifetimes, high fuel burnup, etc. are good examples of achievements to date that have improved the economics of fast neutron systems. The IAEA, through its Technical Working Group on Fast Reactors (TWG-FR) and Technical Working Group on Nuclear Fuel Cycle Options and Spent Fuel Management (TWG-NFCO), devotes many of its initiatives to encouraging technical cooperation and promoting common research and technology development projects among Member States with fast reactor and advanced fuel cycle development programmes, with the general aim of catalysing and accelerating technology advances in these fields. In particular the theme of fast reactor deployment, scenarios and economics has been largely debated during the recent IAEA International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, held in Paris in March 2013. Several papers presented at this conference discussed the economics of fast reactors from different national and regional perspectives, including business cases, investment scenarios, funding mechanisms and design options that offer significant capital and energy production cost reductions. This Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics addresses Member States’ expressed need for information exchange in the field, with the aim of identifying the main open issues and launching possible initiatives to help and

  15. Report on the IAEA technical meeting on co-ordination of the network of nuclear reaction data centres

    International Nuclear Information System (INIS)

    Schwerer, O.

    2003-08-01

    Results of the IAEA Technical Meeting on the Co-ordination of the Network of Nuclear Reaction Data Centres held at the IAEA Headquarters, Vienna, Austria, 17 to 19 June 2003, are summarised in this report. The meeting was attended by 14 participants from 9 cooperating data centres of five member states and two International Organizations. A meeting summary, the conclusions and actions, progress and status reports of the participating data centres, and working papers considered at the meeting, are given in the relevant sections. (author)

  16. Proceedings of the seventh annual gasification and gas stream cleanup systems contractors review meeting: Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Ghate, M.R.; Markel, K.E. Jr.; Jarr, L.A.; Bossart, S.J. (eds.)

    1987-08-01

    On June 16 through 19, 1987, METC sponsored the Seventh Annual Gasification and Gas Stream Cleanup Systems Contractors Review Meeting which was held at the Sheraton Lakeview Conference Center in Morgantown, West Virginia. The primary purpose of the meeting was threefold: to review the technical progress and current status of the gasification and gas stream cleanup projects sponsored by the Department of Energy; to foster technology exchange among participating researchers and other technical communities; to facilitate interactive dialogues which would identify research needs that would make coal-based gasification systems more attractive economically and environmentally. More than 310 representatives of Government, academia, industry, and foreign energy research organizations attended the 4-day meeting. Fifty-three papers and thirty poster dsplays were presented summarizing recent developments in the gasification and gas stream cleanup programs. Volume II covers papers presented at sessions 5 and 6 on system for the production of synthesis gas, and on system for the production of power. All papers have been processed for inclusion in the Energy Data Base.

  17. Proceedings of the seventh annual gasification and gas stream cleanup systems contractors review meeting: Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Ghate, M.R.; Markel, K.E. Jr.; Jarr, L.A.; Bossart, S.J. (eds.)

    1987-08-01

    On June 16 through 19, 1987, METC sponsored the Seventh Annual Gasification and Gas Stream Cleanup Systems Contractors Review Meeting which was held at the Sheraton Lakeview Conference Center in Morgantown, West Virginia. The primary purpose of the meeting was threefold: to review the technical progress and current status of the gasification and gas stream cleanup projects sponsored by the Department of Energy; to foster technology exchange among participating researchers and other technical communities; to facilitate interactive dialogues which would identify research needs that would make coal-based gasification systems more attractive economically and environmentally. More than 310 representatives of Government, academia, industry, and foreign energy research organizations attended the 4-day meeting. Fifty-three papers and thirty poster displays were presented summarizing recent developments in the gasification and gas stream cleanup programs. Volume I covers information presented at sessions 1 through 4 on systems for the production of Co-products and industrial fuel gas, environmental projects, and components and materials. Individual papers have been processed for the Energy Data Base.

  18. Theoretical and experimental studies of heavy liquid metal thermal hydraulics. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2006-10-01

    Through the Nuclear Energy Department's Technical Working Group on Fast Reactors (TWG-FR), the IAEA provides a forum for exchange of information on national programmes, collaborative assessments, knowledge preservation, and cooperative research in areas agreed by the Member States with fast reactor and partitioning and transmutation development programmes (e.g. accelerator driven systems (ADS)). Trends in advanced fast reactor and ADS designs and technology development are periodically summarized in status reports, symposia, and seminar proceedings prepared by the IAEA to provide all interested IAEA Member States with balanced and objective information. The use of heavy liquid metals (HLM) is rapidly diffusing in different research and industrial fields. The detailed knowledge of the basic thermal hydraulics phenomena associated with their use is a necessary step for the development of the numerical codes to be used in the engineering design of HLM components. This is particularly true in the case of lead or lead-bismuth eutectic alloy cooled fast reactors, high power particle beam targets and in the case of the cooling of accelerator driven sub-critical cores where the use of computational fluid dynamic (CFD) design codes is mandatory. Periodic information exchange within the frame of the TWG-FR has lead to the conclusion that the experience in HLM thermal fluid dynamics with regard to both the theoretical/numerical and experimental fields was limited and somehow dispersed. This is the case, e.g. when considering turbulent exchange phenomena, free-surface problems, and two-phase flows. Consequently, Member States representatives participating in the 35th Annual Meeting of the TWG-FR (Karlsruhe, Germany, 22-26 April 2002) recommended holding a technical meeting (TM) on Theoretical and Experimental Studies of Heavy Liquid Metal Thermal Hydraulics. Following this recommendation, the IAEA has convened the Technical Meeting on Theoretical and Experimental Studies of

  19. 76 FR 8381 - Proposal Review for Physics; Notice of Meeting

    Science.gov (United States)

    2011-02-14

    ... NATIONAL SCIENCE FOUNDATION Proposal Review for Physics; Notice of Meeting In accordance with the... advice and recommendations concerning progress of the Center for Magnetic Self-Organization in Laboratory.... 552b(c), of the Government in the Sunshine Act. Dated: February 9, 2011. Suzanne H. Plimpton, Reports...

  20. 78 FR 25309 - Proposal Review Panel Physics; Notice of Meeting

    Science.gov (United States)

    2013-04-30

    ...: 703-292-8783. Purpose of Meeting: To review the progress of the Center for the Physics of Living Cells...--Welcome and Presentation of PFC. 10:00 a.m.-12:00 noon Closed--Science and Future plans reports. 12:00....m.-5:00 p.m. Closed--Executive Sessions: Science and Future Plans Presentations, Outreach and...

  1. 78 FR 29780 - Proposal Review Panel Physics; Notice of Meeting

    Science.gov (United States)

    2013-05-21

    ... Proposal Review Panel Physics; Notice of Meeting In accordance with the Federal Advisory Committee Act (Pub... for Nuclear Physics; National Science Foundation, 4201 Wilson Blvd., Arlington, VA 22230. Telephone..., Operations, Upgrades and Commissioning Overview 10:15 a.m.-11:15 a.m. Open--Accelerator Physics Research, and...

  2. Supporting design reviews with pre-meeting virtual reality environments

    NARCIS (Netherlands)

    van den Berg, Marc Casper; Hartmann, Timo; de Graaf, Robin S.

    2017-01-01

    The purpose of this paper is to explore how design reviews can be supported with pre-meeting virtual reality environments. Previous research has not systematically investigated how virtual environments can be used to communicate the design intent (to clients) and to communicate feedback (to design

  3. Technical meeting of project counterparts on 'Cyclotron production of Iodine-123'. Report

    International Nuclear Information System (INIS)

    2002-01-01

    Several cyclotron laboratory facilities are very much interested in the production of Iodine-123 for medical applications in view of its optimal physical and chemical properties. Some of these countries have in the past used the solid target technology based on utilization of enriched Tellurium targets and are currently involved in the development of enriched Xenon-124 gas targets to improved radionuclidic purity as required by the needs of modern nuclear medicine. With the purpose of discussing the advances in the later route of production and to foster mutual co-operation among the developing countries interested in this technology, a meeting was convened with the participation of scientists from Argentina, Brazil, Iran, Korea and Syria. A scientist from the United States was also invited as an expert to provide advise on particular aspects of the technology. This publication contains as an annex technical reports from the participating institutions. All of these reports have been separately indexed and provided with abstracts

  4. Diagnostic systems in nuclear power plants. Proceedings of a technical committee meeting. Working material

    International Nuclear Information System (INIS)

    1998-01-01

    Nuclear power industry has a quite long tradition in on-line diagnostic of mechanical components and a considerable effort was put in developing diagnostic systems which are able to detect arising mechanical problems at an early stage. Computers are increasingly exploited to provide higher level information on process behaviour such as: early indication of the process deviation from normal conditions; rapid identification of the cause of any disturbance; prediction of the evolution of a disturbance; operator aid through computerized help. Following the recommendation of Several Member States to strengthen the activity in this field two divisions of IAEA established in 1995 the International Task Force on Nuclear Power Plant Diagnostics. The scope of the task force cover both technological developments and safety/licensing aspects of diagnostics. This report contains papers presented at the last in the series of Technical Committee Meetings on the Diagnostic Systems in Nuclear Power Plants organized in the framework of International Task Force

  5. Facilitating Site Specific and Citizens Advisory Boards: Running Effective Meetings that Involve Complex Technical Issues

    International Nuclear Information System (INIS)

    Freeman, J.

    2009-01-01

    Environmental cleanup issues at federal sites are more often than not on the agendas of meetings of the Site Specific Advisory Boards (SSABs), also called Citizens Advisory Boards (CABs), that exist at most U.S. Department of Energy (DOE) sites with an Environmental Management (EM) mission. In 1994, when Congress established these committees comprised of local citizens, it enabled community stakeholders to become more directly involved in DOE EM cleanup decisions. This involvement is to help the agency make cost-effective and environmentally sound decisions which lead to faster, safer cleanups. Eight local Boards that fall under the Federal Advisory Committee Act-chartered EM SSAB charter are found in Hanford, Washington; Idaho; Northern New Mexico; Nevada; Oak Ridge, Tennessee; Paducah, Kentucky; Portsmouth, Ohio; and at the Savannah River Site in South Carolina. These boards provide advice and recommendations about EM site-specific issues such as cleanup standards (how clean is clean?), environmental restoration, waste management, the stabilization and disposal of non-stockpile nuclear materials, future land use and long-term stewardship, risk assessment and management, and cleanup science and technology activities. These issues are, by their very nature, loaded with complicated technical terms and strategies, scientific data and interpretations, and long histories of studies and reports. The members of SSABs and CABs rotate on and off the Boards according to defined terms of office, thereby routinely opening the Boards' ranks to new members, many of whom are new to the issues. In addition, members of the public who have access to public comment periods at each Board meeting run up against the same daunting menu of obscure acronyms, scientific terms and notations, and an historical trail which is not always evident except to those involved with the issues over many years. How does a facilitator effectively guide such a group of citizens, each of whom arrives to

  6. Performance of operating and advanced light water reactor designs. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2001-10-01

    Nuclear power can provide security of energy supply, stable energy costs, and can contribute to greenhouse gas reduction. To fully realize these benefits, a continued and strong focus must be maintained on means for assuring the economic competitiveness of nuclear power relative to alternatives. Over the past several years, considerable improvements have been achieved in nuclear plant performance. Worldwide, the average energy availability factor has increased from 66 per cent in 1980 to 81 per cent in 1999, with some utilities achieving significantly higher values. This is being achieved through integrated programmes including personnel training and quality assurance, improvements in plant system and component design and plant operation, by various means to reduce outage duration for maintenance and refuelling and other scheduled shutdowns, and by reducing the number of forced outages. Application of technical means for achieving high performance of nuclear power plants is an important element for assuring their economic competitiveness. For the current plants, proper management includes development and application of better technologies for inspection, maintenance and repair. For future plants, the opportunity exists during the design phase to incorporate design features and technologies for achieving high performance. This IAEA Technical Committee meeting (TCM) provided a forum for information exchange on design features and technologies incorporated into LWR plants commissioned within the last 15-20 years, and into evolutionary LWR designs still under development, for achieving performance improvements with due regard to stringent safety requirements and objectives. It also addressed on-going technology development expected to achieve further improvements and/or significant cost reductions. The TCM was attended by 32 participants from 14 Member States: Argentina, Bulgaria, Czech Republic, Finland, France, Germany, Hungary, Japan, Republic of Korea, Mexico

  7. Review of Sodium and Plutonium related Technical Standards in Trans-Uranium Fuel Fabrication Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Misuk; Jeon, Jong Seon; Kang, Hyun Sik; Kim, Seoung Rae [NESS, Daejeon (Korea, Republic of)

    2016-10-15

    In this paper, we would introduce and review technical standards related to sodium fire and plutonium criticality safety. This paper may be helpful to identify considerations in the development of equipment, standards, and etc., to meet the safety requirements in the design, construction and operating of TFFF, KAPF and SFR. The feasibility and conceptual designs are being examined on related facilities, for example, TRU Fuel Fabrication Facilities (TFFF), Korea Advanced Pyro-process Facility (KAPF), and Sodium Cooled Fast Reactor (SFR), in Korea. However, the safety concerns of these facilities have been controversial in part because of the Sodium fire accident and Plutonium related radiation safety caused by transport and handling accident. Thus, many researches have been performed to ensure safety and various documents including safety requirements have been developed. In separating and reducing the long-lived radioactive transuranic(TRU) in the spent nuclear fuel, reusing as the potential energy of uranium fuel resources and reducing the high level wastes, TFFF would be receiving the attention of many people. Thus, people would wonder whether compliance with technical standards that ensures safety. For new facility design, one of the important tasks is to review of technical standards, especially for sodium and Plutonium because of water related highly reactive characteristics and criticality hazard respectively. We have introduced and reviewed two important technical standards for TFFF, which are sodium fire and plutonium criticality safety, in this paper. This paper would provide a brief guidance, about how to start and what is important, to people who are responsible for the initial design to operation of TFFF.

  8. Hot Cell Post-Irradiation Examination and Poolside Inspection of Nuclear Fuel. Proceedings of the IAEA-HOTLAB Technical Meeting

    International Nuclear Information System (INIS)

    2013-04-01

    The growing operational requirements for nuclear fuel, such as longer fuel cycles, higher burnups and wider use of transient regimes, require more robust fuel designs and more radiation resistant materials. Development of such advanced fuels is only possible with testing and analysis of their performance and application of adequate post-irradiation examination (PIE) methods and techniques. In addition, operational feedback data from poolside and PIE facilities are absolutely necessary for verification of fuel modelling codes and analysis of fuel failure mechanisms. For these reasons, the International Atomic Energy Agency (IAEA) has supported the international exchange of knowledge and sharing of best practices in the application of modern destructive and non-destructive methods of investigation of highly radioactive materials through a series of technical meetings (TMs), the last of which was held in 2006 in Buenos Aires. Since 1963, similar meetings, initially at the European level, have been organized by the Hot Laboratories and Remote Handling Working Group (HOTLAB), a partner in the development of the IAEA's Post Irradiation Examination Facilities Database (PIEDB), part of the IAEA's Integrated Nuclear Fuel Cycle Information System. With this successful partnership in mind, in 2010 the IAEA Technical Working Group on Fuel Performance and Technology recommended that a joint IAEA-HOTLAB TM be held on 'Hot Cell Post-Irradiation Examination and Pool-Side Inspection of Nuclear Fuel', covering questions relevant to the IAEA sub-programmes on 'Nuclear Power Reactor Fuel Engineering' and 'Management of Spent Fuel from Nuclear Power Reactors'. The TM was held on 23-27 May 2011, in Smolenice, Slovakia, with the participation of a large number of interested organizations and comprehensive coverage of major PIE and poolside inspection issues relating to both operation and storage of fuel for nuclear power reactors. The proceedings, summaries and conclusions of that joint

  9. Technical Review Board Chairperson Guidelines for Conducting Technical Review Boards for Rocket Testing

    Science.gov (United States)

    2011-08-17

    database with the boxes checked for full text documents only and scholarly journals , including peer-reviewed. Searches were performed using the following...specific topics related to dleir area t:A elt ,pWtiM. Tale the ist of topics and come 1.4) ’Mith a preliminary ~an of who wll be ~viewing which...Surveys. The Journal of Marketing, 12 (2), 145-157. Deming, W. (1952-1953). Statistical Techniques and International Trade. Journal of Marketing, 17

  10. Independent technical review of the Hanford Tank Farm Operations

    International Nuclear Information System (INIS)

    1992-07-01

    The Independent Technical Assessment of the Hanford Tank Farm Operations was commissioned by the Assistant Secretary for Environmental Restoration and Waste Management on November 1, 1991. The Independent Technical Assessment team conducted on-site interviews and inspections during the following periods: November 18 to 22,1991; April 13 to 17; and April 27 to May 1, 1992. Westinghouse Hanford Company is the management and operating contractor for the Department of Energy at the Hanford site. The Hanford Tank Farm Operations consists of 177 underground storage tanks containing 61 million gallons of high-level radioactive mixed wastes from the chemical reprocessing of nuclear fuel. The Tank Farm Operations also includes associated transfer lines, ancillary equipment, and instrumentation. The Independent Technical Assessment of the Hanford Tank Farm Operations builds upon the prior assessments of the Hanford Waste Vitrification System and the Hanford Site Tank Waste Disposal Strategy.The objective of this technical assessment was to determine whether an integrated and sound program exists to manage the tank-waste storage and tankfarm operations consistent with the Assistant Secretary for Environmental Restoration and Waste Management's guidance of overall risk minimization. The scope of this review includes the organization, management, operation, planning, facilities, and mitigation of the safety-concerns of the Hanford Tank Waste Remediation System. The assessments presented in the body of this report are based on the detailed observations discussed in the appendices. When the assessments use the term ''Hanford'' as an organizational body it means DOE-RL and Westinghouse Hanford Company as a minimum, and in many instances all of the stake holders for the Hanford site

  11. First interim project review meeting on management of water hyacinth

    International Nuclear Information System (INIS)

    1980-01-01

    The first project planning meeting was held in New Delhi during 1978 and the second, a project review meeting, in Papua New Guinea during June 1979, both funded by UNEP. Reports from the regional coordinators for Bangladesh, Malaysia, Sri Lanka, Fiji and India are presented. Also presented are reports from the national coordinators for Malaysia, Bangladesh and India. Two visits (a visit to India, Bangladesh and Sri Lanka to study the feasibility of making a film on the work done with water hyacinth and a visit to the U.S. by the regional project coordinator) are also described

  12. 1990 DOE/SANDIA crystalline photovoltaic technology project review meeting

    Energy Technology Data Exchange (ETDEWEB)

    Ruby, D.S. (ed.)

    1990-07-01

    This document serves as the proceedings for the annual project review meeting held by Sandia's Photovoltaic Cell Research Division and Photovoltaic Technology Division. It contains information supplied by each organization making a presentation at the meeting, which was held August 7 through 9, 1990 at the Sheraton Hotel in Albuquerque, New Mexico. Sessions were held to discuss national photovoltaic programs, one-sun crystalline silicon cell research, concentrator silicon cell research, concentrator 3-5 cell research, and concentrating collector development.

  13. Nuclear Fuel Safety Criteria Technical Review - Second edition

    International Nuclear Information System (INIS)

    Beck, Winfried; Blanpain, Patrick; Fuketa, Toyoshi; Gorzel, Andreas; Hozer, Zoltan; Kamimura, Katsuichiro; Koo, Yang-Hyun; Maertens, Dietmar; Nechaeva, Olga; Petit, Marc; Rehacek, Radomir; Rey-Gayo, Jose Maria; Sairanen, Risto; Sonnenburg, Heinz-Guenther; Valach, Mojmir; Waeckel, Nicolas; Yueh, Ken; Zhang, Jinzhao; Voglewede, John

    2012-01-01

    Most of the current nuclear fuel safety criteria were established during the 1960's and early 1970's. Although these criteria were validated against experiments with fuel designs available at that time, a number of tests were based on unirradiated fuels. Additional verification was performed as these designs evolved, but mostly with the aim of showing that the new designs adequately complied with existing criteria, and not to establish new limits. In 1996, the OECD Nuclear Energy Agency (NEA) reviewed existing fuel safety criteria, focusing on new fuel and core designs, new cladding materials and industry manufacturing processes. The results were published in the Nuclear Fuel Safety Criteria Technical Review of 2001. The NEA has since re-examined the criteria. A brief description of each criterion and its rationale are presented in this second edition, which will be of interest to both regulators and industry (fuel vendors, utilities)

  14. Tailoring the Systems Engineering Technical Review Implementation Within Naval Acquisition

    Science.gov (United States)

    2017-09-01

    they can become a computer guru by buying the latest and greatest product that a salesperson can talk them into, and don’t seem to realize that all...thinks they can become a computer guru by buying the latest and greatest product that a salesperson can talk them into, and don’t seem to realize that...adjudication process, and when stakeholders feel the review is ready to be closed. 8 The program had metrics set to meet threshold and objective criteria 9

  15. 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

  16. 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)

  17. Summary record of the twenty-third meeting, (technical sessions), Chalk River, Canada, 27 Sep - 1 Oct 1982

    International Nuclear Information System (INIS)

    Qaim, S.

    The technical sessions deal with advances in nuclear data measurements and newer facilities (with special attention paid to data for fission and fusion reactors); advances in nuclear data evaluations (regional activities and joint evaluated file); activities of nuclear data centres; report on recent NEA meetings; subcommittee reports

  18. IAEA technical committee meeting on national NPP personnel training and qualification programmes. Meeting of the Technical Working Group on Training and Qualification of Nuclear Power Plant Personnel (TWG-T-Q). Working material

    International Nuclear Information System (INIS)

    2003-01-01

    The Technical Working Group on Training and Qualification of Nuclear Power Plant Personnel (TWG-T and Q) was established by the Director General of the IAEA in 1994. With the dissolution of the UNIPEDE NPP training group, the TWG-T and Q is considered very important service it is the only international group of experts in the subject area. Objectives of the Meeting: to exchange information on status and trends concerning NPP personnel training and qualification in Member States; to recommend future IAEA activities related to NPP personnel training and qualification; to review the Agency activities on the subject area performed in 2002-2003 and provide recommendations to implement the IAEA programme in 2004-2005. This report is intended for Members of the TWG-T and Q as a record of the work of this group, as well as a general source of information for others who are involved in activities related to the training and qualification of NPP personnel

  19. A quick look at the post accident review meeting (PARM)

    International Nuclear Information System (INIS)

    Dastur, A.; Osborne, R.; Pendergast, D.; Primeau, D.B.; Snell, V.G.; Torgerson, D.

    1986-01-01

    The IAEA sponsored Post-Accident Review Meeting (PARM) for Chernobyl took place in Vienna from August 25 to 29, 1986. A report by the International Nuclear Safety Advisory Group (INSAG) and the group of experts supporting them is under preparation and will be available later in September. In view of the importance of the meeting, this report has been prepared by the AECL Conference delegation to provide more rapid feedback. Since digestion of the information will take much more time, we have attempted to stick to what we heard, avoiding speculation unless absolutely necessary. Since the Chernobyl event was so serious, it is essential that the root causes be identified, in order to avoid a related occurrence. It is necessary that the design and operation of CANDU reactors be carefully reviewed to identify, if any, of the lessons have any relevance. This must be done thoroughly and without complacency

  20. Advanced fuel pellet materials and designs for water cooled reactors. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2004-10-01

    This meeting was the second IAEA meeting on this subject. The first was held in 1996 in Tokyo, Japan. They are all part of a cooperative effort through the Technical Working Group on Water Reactor Fuel Performance and Technology (TWGFPT) of IAEA, with a series of three further meetings organized by CEA, France and co-sponsored by the IAEA and OECD/NEA. In the seven years since the first meeting took place, the demands on fuel duties have increased, with higher burnup, longer fuel cycles and higher temperatures. This places additional demands on fuel performance to comply with safety requirements. Criteria relative to fuel components, i.e. pellets and fuel rod column, require limiting of fission gas release and pellet-cladding interaction (PCI). This means that fuel components should maintain the composite of rather contradictory properties from the beginning until the end of its in-pile operation. Fabrication and design tools are available to influence, and to some extent, to ensure desirable in-pile fuel properties. Discussion of these tools was one of the objectives of the meeting. The second objective was the analysis of fuel characteristics at high burnup and the third and last objective was the discussion of specific feature of MOX and urania gadolinia fuels. Sixty specialists in the field of fuel fabrication technology attended the meeting from 18 countries. Twenty-five papers were presented in five sessions covering all relevant topics from the practices and modelling of fuel fabrication technology to its optimization. Eight papers were presented in session 'Optimization of fuel fabrication technology' which all were devoted to fuel fabrication technology. They mostly treated methods for optimizing fuel manufacturing processes, but gave also a good overview on nuclear fabrication needs and capabilities in different countries. During Session 'UO 2 , MOX and UO 2 -Gd 2 O 3 pellets with additives', six papers were presented in this session, which dealt mainly

  1. 78 FR 16301 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2013-03-14

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics; Notice of Meeting In accordance... announces the following meeting. Name: LIGO Annual Review Site Visit at Hanford Observatory for Physics... Physics, National Science Foundation, Arlington, VA (703) 292-4432. [[Page 16302

  2. 75 FR 81315 - Earth Sciences Proposal Review Panel; Notice of Meeting

    Science.gov (United States)

    2010-12-27

    ... NATIONAL SCIENCE FOUNDATION Earth Sciences Proposal Review Panel; Notice of Meeting In accordance... announces the following meeting. Name: Proposal Review Panel in Earth Sciences (1569). Date and Time... Kelz, Program Director, Instrumentation & Facilities Program, Division of Earth Sciences, Room 785...

  3. Tenth Technical Advisory Group (TAG) meeting on vaccine-preventable diseases.

    Science.gov (United States)

    1992-04-01

    In march 1992, participants met in Rio de Janeiro, Brazil for the 10th Meeting of the PAHO Technical Advisory Group (TAG) on Vaccine-Preventable Diseases. Immunization coverage for all vaccines exceeded 75%. In 1991, only 9 confirmed cases of wild poliovirus occurred out of 4000 stool specimens examined. These cases were in Colombia and Peru. Many national immunization days and mop-up operations complement routine immunization services and have contributed greatly to interruption of the wild poliovirus in the Americas. Social mobilization efforts and mass media campaigns have increased coverage rates nationally and regionally. Surveillance efforts continue to improve. Almost 20,000 health units in Latin America report each week on the existence or nonexistence of acute flaccid paralysis cases. TAG continues to prefer the oral polio vaccine for the eradication program in the Americas. Participants discussed issues pertaining to certification of polio eradication. Measles incidence in the Americas is still falling and intervals between outbreaks are growing. Some countries in the English-speaking Caribbean using a month long, mass vaccination strategy have apparently interrupted measles transmission. Since measles causes more deaths than any other vaccine preventable disease, PAHO's TAG places it as the highest priority. The proportion of neonatal tetanus cases that are being investigated is growing (1991=8% and 1990=35%). Participants challenged Venezuela and Panama to vaccinate 100% of reproductive age women in high risk areas before the next meeting. Inadequate data on pertussis prevents PAHO from measuring any changes in pertussis epidemiology. Some countries have set up systems to monitor adverse events associated with vaccination. Participants agreed that member nations should begin hepatitis B vaccination programs for high risk groups.

  4. Effects and effectiveness of dynamic arm supports: a technical review.

    Science.gov (United States)

    van der Heide, Loek A; Gelderblom, Gert Jan; de Witte, Luc P

    2015-01-01

    Numerous dynamic arm supports have been developed in recent decades to increase independence in the performance of activities of daily living. Much effort and money have been spent on their development and prescription, yet insight into their effects and effectiveness is lacking. This article is a systematic review of evaluations of dynamic arm supports. The 8 technical evaluations, 12 usability evaluations, and 27 outcome studies together make 47 evaluations. Technical evaluations were often used as input for new developments and directed at balancing quality, forces and torques, and range of motion of prototypes. Usability studies were mostly single-measure designs that had varying results as to whether devices were usable for potential users. An increased ability to perform activities of daily living and user satisfaction were reported in outcome studies. However, the use of dynamic arm supports in the home situation was reported to be low. Gaining insight into why devices are not used when their developers believe them to be effective seems crucial for every new dynamic arm support developed. The methodological quality of the outcome studies was often low, so it is important that this is improved in the future.

  5. 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)

  6. Summary report of the technical meeting on intermediate-term nuclear data needs for medical applications: cross sections and decay data

    International Nuclear Information System (INIS)

    Nichols, Alan L.; Qaim, Syed M.; Noy, Roberto Capote

    2011-09-01

    A summary is given of a Technical Meeting on 'Intermediate-term Nuclear Data Needs for Medical Applications: Cross Sections and Decay Data'. Participants assessed and reviewed cross-section and decay data for an extensive number of radionuclides deemed as potentially suitable for application in nuclear medicine and radiotherapy. Technical discussions are described in this report, along with comprehensive listings and detailed recommendations for future work. Recommendations focused on cross-section studies for a reasonably wide range of targets and projectiles, along with decay data measurements for specific radionuclides. Cross-section and decay-data evaluations are also merited to ensure the necessary quality and consistency of the data to be assembled in an appropriate IAEA-NDS database. (author)

  7. PREFACE: Third IAEA Technical Meeting on ECRH Physics and Technology in ITER

    Science.gov (United States)

    Cirant, S.

    2005-01-01

    This meeting belongs to a series of topical events which the International Atomic Energy Agency (IAEA, Vienna) organizes in a regular basis on crucial aspects of nuclear fusion research, or related in particular to ITER physics or a technological application relevant to the nuclear fusion reactor. Each Technical Meeting series has a specific object; the events are called on a two-three years basis and are recommended by the IAEA advisory body for Fusion, the International Fusion Research Council (IFRC) . The object of the IAEA-TM held in Como, Italy, 2-5 May 2005, was the application in ITER of powerful Electron Cyclotron waves in the millimeter wave frequency range for plasma Heating and noninductive Current Drive. The meeting was the third on this subject. There were 42 presentations to an audience of about 60 delegates from 16 countries. The main goal of this series of IAEA-TM is to bring together specialists of the different branches involved in the project, in the effort of the best understanding of the limits and capabilities of each one of the different fields of research and development. Millimeter-wave source developers, millimeter-wave system designers and plasma physicists, theoreticians and experimentalists in all of the fields, exposed their way of addressing the problem in plenary sessions attended by all participants. Discussions on the different topics of gyrotron development, launcher options and physics application were continued in forums following the presentations. The specialist reader will find in this volume in particular the latest developments concerning the frequency, the output power and the efficiency of the gyrotrons which are now being considered the preferred type of high power millimeter wave generators for ECH/ECCD applications in the fusion reactor. The debate on the launcher of the EC waves, in the form of Gaussian beams, is presently very active, with a few options on the table to be merged in one optimized and integrated design

  8. Second Annual AEC Scientific Computer Information Exhange Meeting. Proceedings of the technical program theme: computer graphics

    Energy Technology Data Exchange (ETDEWEB)

    Peskin,A.M.; Shimamoto, Y.

    1974-01-01

    The topic of computer graphics serves well to illustrate that AEC affiliated scientific computing installations are well represented in the forefront of computing science activities. The participant response to the technical program was overwhelming--both in number of contributions and quality of the work described. Session I, entitled Advanced Systems, contains presentations describing systems that contain features not generally found in graphics facilities. These features can be roughly classified as extensions of standard two-dimensional monochromatic imaging to higher dimensions including color and time as well as multidimensional metrics. Session II presents seven diverse applications ranging from high energy physics to medicine. Session III describes a number of important developments in establishing facilities, techniques and enhancements in the computer graphics area. Although an attempt was made to schedule as many of these worthwhile presentations as possible, it appeared impossible to do so given the scheduling constraints of the meeting. A number of prospective presenters 'came to the rescue' by graciously withdrawing from the sessions. Some of their abstracts have been included in the Proceedings.

  9. Technologies for improving the availability and reliability of current and future water cooled nuclear power plants. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1998-11-01

    One of the activities of the IAEA is to provide all Member States with an international source of balanced, objective information on advanced in technology for water cooled reactors. Since the global nuclear industry has a common interest in improving plant availability and reliability to assure specific individual plant and country perspective as well as to have an image of well managed competitive industry, the IAEA held a Technical Committee Meeting on Technologies for Improving the Availability and Reliability of Current and Future Water Cooled Nuclear Power Plants in September 1997. The basic aim to was to identify, review and exchange information on international developments in technologies for achieving high availability and reliability and to suggest areas where further technical advances could contribute to improvement of performance. Designs for future plants were presented in the context of how they can accommodate both the organizational and technical means for reaching even higher levels of performance. This proceedings contains the contributed papers presented at this Meeting each with a separate abstract. Four sessions were concerned with: policies, practices and procedures for achieving high reliability and availability; improving availability and reliability through better use of today's technologies; recent advances in technologies for improving availability and reliability; achieving high availability for new plants

  10. Operational and decommissioning experience with fast reactors. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2004-08-01

    aspect of this knowledge base is given by the accumulated operational experience. The participants in the 33rd and the 34th Annual Meeting of the International Working Group on Fast Reactors, recommended holding a technical meeting (TM) on Feedback from Operational and Decommissioning Experience with Fast Reactors, and to launch a Co-ordinated Research Project (CRP) on Generalization and Analyses of Operational Experience with Fast Reactor Equipment and Systems (Preserve Fast Reactor Operation and Decommissioning Experience). The scope of the TM was to provide a global forum for information exchange on fast reactor operational and decommissioning experience. The objectives of the TM were to: Exchange detailed technical information on fast reactor operation and/or decommissioning experience with DFR, PFR (UK); KNK-II (Germany); Rapsodie, Phenix, Superphenix (France); BR-10, BOR-60, BN-600 (Russian Federation); BN-350 (Kazakhstan); SEFOR, EBR-II, Fermi, FFTF (USA.); FTBR (India); JOYO, MONJU (Japan); Present the status of the work concerning the knowledge preservation efforts related to the experience accumulated in the various member states from the operation and decommissioning of fast reactors; Start the preparation of the planned Co-ordinated Research Project (CRP) on Generalization and Analyses of Operational Experience with Fast Reactor Equipment and Systems

  11. CANMET Materials Technology Laboratory technical review 2003-2004

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This technical review described research activities of the CANMET Materials Technology Laboratory, whose mandate is to develop and deploy technologies that improve aspects of producing and using products derived from minerals and metals. During the reporting period, 126 reports for clients were published and the lab participated in 15 national and international consortia. The Advanced Concrete Technology Program was reviewed. The Advanced Materials Technologies Program was discussed, and recent advances in the hydroforming of tubes and corrosion protection techniques for magnesium used in automobiles were presented. A review of the Sustainable Casting Program was presented. New materials for the mining industry were discussed, as well as issues concerning lost-foam casting. Details of the Efficient Metal Production Program were provided and new galvanized TRIP steel and metal inert gas welding processes were outlined. New additions to the Infrastructure Reliability Program included intelligent systems for pipeline infrastructure reliability; software for corrosion control; and risk management of pipelines. Additions to the Certifying Agency for Non-Destructive Testing included a new certification of X-Ray Fluorescence operators and revisions to the non-destructive testing qualification and certification of personnel. New patents developed by the laboratory included a hydrogen sensor using a solid hydrogen ion conducting electrolyte; reinforcement preform for the production of magnesium composite and other metal matrix composite materials; a rechargeable battery electrode testing device; a sulfide biosensor; and a bio-corrosion probe. During the 2 year review period, staff received 13 national and international awards. An outline of major facilities and equipment was presented, as well as details of new materials for use by the transportation sector. Advances in concrete and other construction materials were outlined, as well as metallurgical process improvements. A

  12. 77 FR 38837 - Medicare Program; Meeting of the Medicare Economic Index Technical Advisory Panel

    Science.gov (United States)

    2012-06-29

    .... Please provide your full name (as it appears on your government-issued photographic identification...: Meeting location: We will be broadcasting the meeting live via webinar and conference call (for audio... adjustment. II. Meeting Format This meeting is open to the public. There will be up to 45 minutes allotted at...

  13. 17th 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, B.J.

    2012-06-01

    The 17th meeting of the Subcommittee on Atomic and Molecular Data of the International Fusion Research Council (IFRC) was held on 27-28 April 2010 at IAEA Headquarters in Vienna, Austria. Activities of the Atomic and Molecular Data Unit for the period 2006-2008 were reviewed, and recommendations were made for the 2010-2011 budget cycle. The proceedings, conclusions and recommendations of the Subcommittee meeting are briefly described in this report. Specific recommendations of the Subcommittee from this meeting, as well as the report on the activities of the IAEA Atomic and Molecular Data Unit for the period May 2006 - March 2008, are also included. (author)

  14. Advances in radiation chemistry of polymers. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2004-11-01

    The meeting on radiation effects on polymers was held at the Radiation Laboratory at the University of Notre Dame to review and discuss advances in the radiation processing of polymers. The trends in the basic research, research and development, and industrial applications were reported. The scope of more applied uses of irradiation involving polymers ranged from discussions of the curing of materials for dental applications, to the effects on polyolefins, the most broadly used class of polymers prevalent in industrial radiation processing, and to emerging interests in hydrogels, carbon fiber composites, heterogeneous mixtures based on material by-products (scrap plastic and wood fragments), grafted materials and materials for electronic uses. In addition, the emerging interests in the use of recently developed high power x ray systems for industrial use were presented. The document contains 12 individual papers, each of them was indexed and abstracted separately

  15. 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

    International Nuclear Information System (INIS)

    Stephens, J.A.

    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)

  16. 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)

  17. 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

  18. PREFACE: 11th IAEA Technical Meeting on H-mode Physics and Transport Barriers

    Science.gov (United States)

    Takizuka, Tomonori

    2008-07-01

    This volume of Journal of Physics: Conference Series contains papers based on invited talks and contributed posters presented at the 11th IAEA Technical Meeting on H-mode Physics and Transport Barriers. This meeting was held at the Tsukuba International Congress Center in Tsukuba, Japan, on 26-28 September 2007, and was organized jointly by the Japan Atomic Energy Agency and the University of Tsukuba. The previous ten meetings in this series were held in San Diego (USA) 1987, Gut Ising (Germany) 1989, Abingdon (UK) 1991, Naka (Japan) 1993, Princeton (USA) 1995, Kloster Seeon (Germany) 1997, Oxford (UK) 1999, Toki (Japan) 2001, San Diego (USA) 2003, and St Petersburg (Russia) 2005. The purpose of the eleventh meeting was to present and discuss new results on H-mode (edge transport barrier, ETB) and internal transport barrier, ITB, experiments, theory and modeling in magnetic fusion research. It was expected that contributions give new and improved insights into the physics mechanisms behind high confinement modes of H-mode and ITBs. Ultimately, this research should lead to improved projections for ITER. As has been the tradition at the recent meetings of this series, the program was subdivided into six topics. The topics selected for the eleventh meeting were: H-mode transition and the pedestal-width Dynamics in ETB: ELM threshold, non-linear evolution and suppression, etc Transport relations of various quantities including turbulence in plasmas with ITB: rotation physics is especially highlighted Transport barriers in non-axisymmetric magnetic fields Theory and simulation on transport barriers Projections of transport barrier physics to ITER For each topic there was an invited talk presenting an overview of the topic, based on contributions to the meeting and on recently published external results. The six invited talks were: A Leonard (GA, USA): Progress in characterization of the H-mode pedestal and L-H transition N Oyama (JAEA, Japan): Progress and issues in

  19. Developments in uranium resources, production, demand and the environment. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2005-01-01

    Globalization has led to growing importance of the uranium production industries of the world's developing countries. Uranium supply from these countries could be increasingly important in satisfying worldwide reactor requirements over time. Along with the increasing contribution to worldwide uranium supply, the environmental impact of uranium production in developing countries has come under increasing scrutiny from the nuclear power industry, the end-users of this supply, and from communities impacted by uranium mining and processing. The papers presented at the meeting on 'Developments in Uranium Resources, Production, Demand and the Environment' provide an important overview of uranium production operations and of their environmental consequences in developing countries, as well as offering insight into future production plans and potential. Along with their increasing contribution to worldwide uranium supply, the environmental impact of uranium production in developing countries has come under increasing scrutiny from the nuclear power industry, the end users of this supply, and by communities impacted by uranium mining and processing. Therefore, the environmental consequences of uranium production were included in the meeting agenda as noted in the meeting title, 'Developments in uranium resources, production, demand and the environment'. Accordingly, the papers presented at this meeting are about evenly divided between discussions of known and potential uranium resources and uranium production technology and the environmental impact of uranium mining and processing, its related remediation technology and its costs. Though emphasis is placed on uranium programmes in developing countries, an overview of COGEMA's worldwide activities is also presented. This presentation provides insight into the strategies of arguably the Western world's most integrated and diversified uranium company, including the geographic diversity of its exploration and production

  20. In situ leach uranium mining. Proceedings of a technical committee meeting. Working material

    International Nuclear Information System (INIS)

    2002-03-01

    mutual interest between specialists who developed and employ the technology in the two areas. The Technical Committee Meeting on In Situ Leach Uranium Mining was held in Almaty, Kazakhstan in the Hall of Science of the National Academy of Science from 9-12 September 1996. It was attended by 61 participants from 15 countries and one non-governmental international organization (Uranium Institute). Organizational support for the meeting was provided on behalf of the Government of the Republic of Kazakhstan by the National Joint Stock Company of Atomic Energy and Industry 'KATEP', the state enterprise responsible for uranium production in the Republic of Kazakhstan. This meeting provided the first ever opportunity for specialists from throughout the world to meet in central Asia and discuss ISL technology with emphasis on its development and use in the region. The site visit to the Number 6 Mining Company in south central Kazakhstan provided an opportunity for participants to observe and discuss an operating ISL facility

  1. Technologies for gas cooled reactor decommissioning, fuel storage and waste disposal. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1998-09-01

    Gas cooled reactors (GCRs) and other graphite moderated reactors have been important part of the world's nuclear programme for the past four decades. The wide diversity in status of this very wide spectrum of plants from initial design to decommissioning was a major consideration of the International Working group on Gas Cooled Reactors which recommended IAEA to convene a Technical Committee Meeting dealing with GCR decommissioning, including spent fuel storage and radiological waste disposal. This Proceedings includes papers 25 papers presented at the Meeting in three sessions entitled: Status of Plant Decommissioning Programmes; Fuels Storage Status and Programmes; waste Disposal and decontamination Practices. Each paper is described here by a separate abstract

  2. Implications of power uprates on safety margins of nuclear power plants. Report of a technical meeting

    International Nuclear Information System (INIS)

    2004-09-01

    The safety of nuclear power plants (NPPs) is based on the defence in depth concept, which relies on successive physical barriers (fuel matrix, cladding, primary system pressure boundary and containment) and other provisions to control radioactive materials and on multiple levels of protection against damage to these barriers. Deterministic safety analysis is an important tool for conforming the adequacy and efficiency of provisions within the defence in depth concept and is used to predict the response of an NPP in predetermined operational states. This type of safety analysis applies a specific set of rules and specific acceptance criteria. Deterministic analysis is typically focused on neutronic, thermohydraulic, radiological and structural aspects, which are often analysed with different computational tools. The advanced computational tools developed for deterministic safety analysis are used for better establishment and utilization of licensing margins or safety margins in consideration of analysis results. At the same time, the existence of such margins ensures that NPPs operate safely in all modes of operation and at all times. To properly assess and address the existing margins and to be able to take advantage of unnecessary conservatisms, state of the art analytical tools intended for safety assessment have been developed. Progress made in the development and application of modern codes for safety analysis and better understanding of phenomena involved in plant design and operation enable the analysts to determine safety margins in consideration of analysis results (licensing margins) with higher precision. There is a general tendency for utilities to take advantage of unnecessarily large conservatisms in safety analyses and to utilize them for reactor power uprates, better utilization of nuclear fuel, higher operational flexibility and for justification of lifetime extension. The present publication sets forth the results of a Technical Meeting on the

  3. 75 FR 18205 - Notice of Peer Review Meeting for the External Peer Review Drafts of Two Documents on Using...

    Science.gov (United States)

    2010-04-09

    ... AGENCY Notice of Peer Review Meeting for the External Peer Review Drafts of Two Documents on Using... announcing that Eastern Research Group, Inc. (ERG), an EPA contractor for external scientific peer review, will convene an independent panel of experts and organize and conduct an external peer review meeting...

  4. 41th Plenary Meeting Report of the Scientific, Technical and Economic Committee for Fisheries (PLEN-12-03)

    DEFF Research Database (Denmark)

    Abella, J. A.; Andersen, J.; Bailey, N.

    The Scientific, Technical and Economic Committee for Fisheries hold its 41st plenary on 5-9 November 2012 in Brussels (Belgium). The terms of reference included both issues assessments of STECF Expert Working Group reports and additional requests submitted to the STECF by the Commission. Topics...... dealt were inter alia assessments of Mediterranean and Black Sea stocks, evaluations of fishing effort regimes, technical measures, review of scientific advice on stocks and fisheries of EU interest, fisheries management plans evaluation issues....

  5. Report of the technical committee meeting on 1996 annual workshop on ASSET experience

    International Nuclear Information System (INIS)

    1996-01-01

    The 1996 ASSET workshop was attended by 27 participants representing 18 countries. This level of support demonstrates the continued interest in the ASSET methodology and in particular the benefit of an International perspective in the analysis of the events at Nuclear Power Plants. Agenda of the meeting and list of participants are included in this report as Attachments 1 and 5 respectively. Papers and/or presentations were made by all countries represented and provided a wide range of views on the use of the ASSET methodology. In general the views of the delegates were positive but inevitably some were critical. The areas of criticism included the perennial problem with the use of the INES ranking procedures to assess event consequences, a perception by some delegates that ASSET is difficult to use and manpower intensive and that the programme for the Peer Review missions is very tight. With the exception of the INES use, the other criticisms were addressed within the working parties that form part of this workshop. The workshop was divided into three task groups to analyse missions at three NPPs, Forsmark, Sweden, Leningrad, Russia and Smolensk, Russia. Although the value of the last mentioned report was limited to the plant's self assessment as the ASSET peer review mission was postponed to later in 1996. Refs, figs, tabs

  6. Technical Meeting (Research Coordination Meeting) of the Coordinated Research Project (CRP) on 'Studies of advanced reactor technology options for effective incineration of radioactive waste'. Working material

    International Nuclear Information System (INIS)

    2005-01-01

    The Technical Meeting held at the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) in Hefei was the second Research Coordination Meeting (RCM) of the CRP on 'Studies of Innovative Reactor Technology Options for Effective Incineration of Radioactive Waste'. All but one Member States participating in the CRP were attending: in all, 26 participants from 13 Member States and three international organizations. The overall objective of the CRP is to increase the capability of Member States in developing and applying advanced nuclear technologies in the area of long-lived radioactive waste utilization and transmutation. The final goal of the CRP is to deepen the understanding of the dynamics of transmutation systems, e.g., the accelerator driven system, especially of systems with deteriorated safety parameters, to qualify the available methods, specify the range of validity of these methods, and formulate requirements for future theoretical developments. Should transient experiments be available, the CRP will pursue experimental benchmarking work. Based on the results, the CRP will conclude on the potential need of transient experiments and make appropriate proposals for experimental programs. The scope of the second RCM was to review the progress achieved with regard on the technical work of the CRP. In particular, the main objectives of the RCM were to (a) analyse and inter-compare the individual results; (b) identify of eventual changes/improvements to the tasks and/or work plans; (c) plan the next stage(s); and (d) start preparation of the final CRP report. The participants were given a brief overview of the Institute's mission and accomplishments. ASIPP (Academia Sinica, Institute of Plasma Physics) was founded in 1978 as the leading centre for high temperature plasma physics, magnetically confined fusion technology, as well as R and D in related technological areas. ASIPP employs nearly 500 staff, of which more than 70% are scientists or engineers

  7. 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)

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

    International Nuclear Information System (INIS)

    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)

  9. Technical feasibility and reliability of passive safety systems for nuclear power plants. Proceedings of an advisory group meeting

    International Nuclear Information System (INIS)

    1996-12-01

    The meeting provided an overview of the key issues on passive safety. Technical problems which may affect future deployment, and the operating experience of passive systems and components, as well as, definitions of passive safety terms, were discussed. Advantages and disadvantages of passive systems were also highlighted. The philosophy behind different passive safety systems was presented and the range of possibility between fully passive and fully active systems was discussed. Refs, figs, tabs

  10. 24 CFR 902.68 - Technical review of results of PHAS Indicators #1 or #4.

    Science.gov (United States)

    2010-04-01

    ... results of PHAS Indicators #1 or #4. (a) Request for technical reviews. This section describes the process... 24 Housing and Urban Development 4 2010-04-01 2010-04-01 false Technical review of results of PHAS Indicators #1 or #4. 902.68 Section 902.68 Housing and Urban Development Regulations Relating to Housing and...

  11. Commercial Crew Program and the Safety Technical Review Board

    Science.gov (United States)

    Mullen, Macy

    2016-01-01

    The Commercial Crew Program (CCP) is unique to any other program office at NASA. After the agency suffered devastating budget cuts and the Shuttle Program retired, the U.S. gave up its human spaceflight capabilities. Since 2011 the U.S. has been dependent on Russia to transport American astronauts and cargo to the International Space Station (ISS) and back. NASA adapted and formed CCP, which gives private, domestic, aerospace companies unprecedented reign over America's next ride to space. The program began back in 2010 with 5 companies and is now in the final phase of certification with 2 commercial partners. The Commercial Crew Program is made up of 7 divisions, each working rigorously with the commercial providers to complete the certification phase. One of these 7 divisions is Systems Engineering and Integration (SE&I) which is partly comprised of the Safety Technical Review Board (STRB). The STRB is primarily concerned with mitigating improbable, but catastrophic hazards. It does this by identifying, managing, and tracking these hazards in reports. With the STRB being in SE&I, it significantly contributes to the overall certification of the partners' vehicles. After the partners receive agency certification approval, they will have the capability to provide the U.S. with a reliable, safe, and cost-effective means of human spaceflight and cargo transport to the ISS and back.

  12. Robotic liver surgery: technical aspects and review of the literature

    Science.gov (United States)

    Bianco, Francesco Maria; Daskalaki, Despoina; Gonzalez-Ciccarelli, Luis Fernando; Kim, Jihun; Benedetti, Enrico

    2016-01-01

    Minimally invasive surgery for liver resections has a defined role and represents an accepted alternative to open techniques for selected cases. Robotic technology can overcome some of the disadvantages of the laparoscopic technique, mainly in the most complex cases. Precise dissection and microsuturing is possible, even in narrow operative fields, allowing for a better dissection of the hepatic hilum, fine lymphadenectomy, and biliary reconstruction even with small bile ducts and easier bleeding control. This technique has the potential to allow for a greater number of major resections and difficult segmentectomies to be performed in a minimally invasive fashion. The implementation of near-infrared fluorescence with indocyanine green (ICG) also allows for a more accurate recognition of vascular and biliary anatomy. The perspectives of this kind of virtually implemented imaging are very promising and may be reflected in better outcomes. The overall data present in current literature suggests that robotic liver resections are at least comparable to both open and laparoscopic surgery in terms of perioperative and postoperative outcomes. This article provides technical details of robotic liver resections and a review of the current literature. PMID:27500143

  13. International Linear Collider Technical Review Committee Report, 1995

    International Nuclear Information System (INIS)

    1995-12-01

    This 1995 report of the International Linear Collider Technical Review Committee is the first attempt to gather in one document the current status of all major e + e - linear collider projects in the world. The report is the result of a collaborative effort of scientists from many laboratories working together over a period of about one year. A short description of the organization, origins and history of the report is given below. To get an idea of the organization, the reader should first refer to the Table of Contents. Chapter 1 is an introduction and general overview of the respective 500 GeV c.m. energy machines. In contrast, Chapter 2, cutting across individual machine boundaries, gives a comparative description and discussion of all the major machine sub-systems as well as particle physics experimentation, showing where these subjects stand today and what additional work needs to be done in the next few years to reach the point where complete design reports can be prepared. Chapter 3 describes the various paths to energy upgrades, and other experimental options (γγ, e - e - , etc.). Chapter 4 gives a short status report of the machine experiments and test facilities being built in the world. Chapter 5 outlines current and other possible areas of collaboration and finally., Chapter 6 summarizes our principal conclusions

  14. International Linear Collider Technical Review Committee Report, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    This 1995 report of the International Linear Collider Technical Review Committee is the first attempt to gather in one document the current status of all major e{sup +}e{sup {minus}} linear collider projects in the world. The report is the result of a collaborative effort of scientists from many laboratories working together over a period of about one year. A short description of the organization, origins and history of the report is given below. To get an idea of the organization, the reader should first refer to the Table of Contents. Chapter 1 is an introduction and general overview of the respective 500 GeV c.m. energy machines. In contrast, Chapter 2, cutting across individual machine boundaries, gives a comparative description and discussion of all the major machine sub-systems as well as particle physics experimentation, showing where these subjects stand today and what additional work needs to be done in the next few years to reach the point where complete design reports can be prepared. Chapter 3 describes the various paths to energy upgrades, and other experimental options ({gamma}{gamma}, e{sup {minus}}e{sup {minus}}, etc.). Chapter 4 gives a short status report of the machine experiments and test facilities being built in the world. Chapter 5 outlines current and other possible areas of collaboration and finally., Chapter 6 summarizes our principal conclusions.

  15. Typing of Methicillin resistant Staphylococcus aureus: A technical review

    Directory of Open Access Journals (Sweden)

    P L Mehndiratta

    2012-01-01

    Full Text Available Increasing prevalence of Methicillin-resistant Staphylococcus aureus (MRSA worldwide is a growing public health concern. MRSA typing is an essential component of an effective surveillance system to describe epidemiological trends and infection control strategies. Current challenges for MRSA typing are focused on selecting the most appropriate technique in terms of efficiency, reliability, ease of performance and cost involved. This review summarises the available information on application, potential and problems of various typing techniques in discriminating the strains and understanding the epidemiology of MRSA strains. The phenotypic methods in general are easier to perform, easier to interpret, cost effective and are widely available, however less discriminatory. The genotypic methods are expensive and technically demanding, however more discriminatory. Newer technologies involving sequencing of various genes are coming up as broadly applicable and high throughput typing systems. Still there is no consensus regarding the single best method for typing of MRSA strains. Phage typing is recommended as first line approach in epidemiological investigation of MRSA strains. PFGE remains the gold standard for characterisation of outbreak strains. DNA sequencing methods including MLST, spa typing, SCCmec typing and toxin gene profile typing are more practical methods for detecting evolutionary changes and transmission events. The choice of typing technique further depends on the purpose of the study, the facilities available and the utility of data generated to answer a desirable research question. A need for harmonisation of typing techniques by following standard protocols is emphasised to establish surveillance networks and facilitate global MRSA control.

  16. Scintigraphic evaluation of duodenogastric reflux. Problems, pitfalls, and technical review.

    Science.gov (United States)

    Drane, W E; Karvelis, K; Johnson, D A; Silverman, E D

    1987-05-01

    Bile reflux has been implicated in the pathogenesis of gastritis, gastric ulcer, and esophagitis. Radionuclide techniques provide the only non-invasive method to detect duodenogastric reflux. To analyze the problems that occur with attempts at quantitation, 55 patients were prospectively evaluated (45 patients with reflux esophagitis or Barrett's esophagus and ten patients with clinical symptoms of bile reflux, four of whom had Bilroth II surgery) with Tc-99m DISIDA, using a fasting technique with gallbladder stimulation by sincalide. Visual duodenogastric reflux occurred in 16 of 55 patients. Overlap of small bowel with the stomach is the major problem for accurate quantitation and occurred in 20 of 55 patients (36%). Overlap of left lobe of the liver occurred in 40 of 55 patients (73%), but its contribution to gastric activity was slight and could be easily subtracted. Reflux was intermittent in six of the 16 positive studies (38%), and continuous computer acquisition is needed to detect its maximum value. Primarily because of the problem of small bowel overlap, scintigraphic evaluation of duodenogastric reflux is only, at best, semi-quantitative. A review of the technical variables used in this examination, as well as potential problems that can occur, is provided.

  17. Early site reviews for nuclear power facilities: procedures and possible technical review options. Draft

    International Nuclear Information System (INIS)

    1978-02-01

    The document provides guidance for utility companies, State and other governmental agencies, and others who may request or may wish to participate in an early review of site suitability issues related to a site proposed for a nuclear power or test reactor. Although the emphasis of this document is on a nuclear electric generating station, the guidance provided can be used for a test reactor or other kinds of reactors. The procedures to be followed by applicants for construction permits and by others are described and the possible significant areas of technical review are delineated

  18. Technologies for the treatment of effluents from uranium mines, mills and tailings. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2002-06-01

    Effluent treatment is an important aspect of uranium mining and milling operations that continues through decommissioning and site rehabilitation. During the life of a mine, effluent treatment is an integral part of the operation with all effluent either being recycled to the mill or processed through a water treatment plant before being released into the environment. During decommissioning and rehabilitation, effluent treatment must continue either through a water treatment plant of by using passive treatment techniques. Because of the recent closing of several uranium mines or mining districts, particularly in eastern Europe, effluent treatment is becoming an ever increasing concern. Therefore the IAEA convened a technical committee meeting (TCM) so that experts from different countries could discuss information and knowledge on effluent treatment processes and methods. The papers presented at the meeting describe techniques for treatment of effluents from uranium production operations - both past and present. This publication contains ten papers presented at the meeting; each of the papers was indexed separately

  19. International Linear Collider Technical Review Committee: Second Report, 2003

    Energy Technology Data Exchange (ETDEWEB)

    Loew, Gregory

    2003-02-21

    As this report is being published, the international high energy physics (HEP) community finds itself confronting a set of fascinating discoveries and new questions regarding the nature of matter and its fundamental particles and forces. The observation of neutrino oscillations that indicates that neutrinos have mass, measurements of the accelerating expansion of the universe that may be due to dark energy, and evidence for a period of rapid inflation at the beginning of the Big Bang are stimulating the entire field. Looming on the horizon are the potential discoveries of a Higgs particle that may reveal the origin of mass and of a whole family of supersymmetric particles that may be part of the cosmic dark matter. For the HEP community to elucidate these mysteries, new accelerators are indispensable. At this time, after careful deliberations, all three regional organizations of the HEP community (ACFA in Asia, HEPAP in North America, and ECFA in Europe) have reached the common conclusion that the next accelerator should be an electron-positron linear collider with an initial center-of-mass energy of 500 Giga-electronvolts (GeV), later upgradable to higher energies, and that it should be built and operated in parallel with the Large Hadron Collider under construction at CERN. Hence, this second report of the International Linear Collider Technical Review Committee (ILC-TRC) comes at a very timely moment. The report was requested by the International Committee on Future Accelerators (ICFA) in February 2001 to assess the current technical status of electron-positron linear collider designs in the various regions. Note that the ILC-TRC was not asked to concern itself with either cost studies or the ultimate selection process of a machine. This Executive Summary gives a short outline of the genesis of the report, the charge given to the committee, and its organization. It then presents a brief description of four electron-positron linear collider designs at hand. The

  20. 75 FR 80511 - Center for Scientific Review; Notice of Closed Meeting

    Science.gov (United States)

    2010-12-22

    ...: Cognition and Perception. Date: January 19-20, 2011. Time: 12 p.m. to 6 p.m. Agenda: To review and evaluate... (Virtual Meeting). Contact Person: Weijia Ni, PhD, Scientific Review Officer, Center for Scientific Review...

  1. 75 FR 37451 - Center for Scientific Review; Notice of Closed Meetings

    Science.gov (United States)

    2010-06-29

    ... for Scientific Review Special Emphasis Panel; Member Conflict: Language and Communication. Date: July... HUMAN SERVICES National Institutes of Health Center for Scientific Review; Notice of Closed Meetings... Committee: Center for Scientific Review Special Emphasis Panel; Member Conflict: Neuroendocrinology and...

  2. Water chemistry and corrosion control of cladding and primary circuit components. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1999-12-01

    Corrosion is the principal life limiting degradation mechanism in nuclear steam supply systems, especially taking into account the trends to increase fuel burnup, thermal rate and cycle length. Primary circuit components of water cooled power reactors have an impact on Zr-based alloys behaviour due to crud (primary circuit corrosion products) formation, transport and deposition on heat transfer surfaces. Crud deposits influence water chemistry, radiation and thermal hydraulic conditions near cladding surface, and by this way-Zr-based alloy corrosion. During the last decade, significant improvements were achieved in the reduction of the corrosion and dose rates by changing the cladding material for one more resistant to corrosion or by the improvement of water chemistry conditions. However, taking into account the above mentioned tendency for heavier fuel duties, corrosion and water chemistry, control will remain a serious task to work with for nuclear power plant operators and scientists, as well as development of generally accepted corrosion model of Zr-based alloys in a water environment in a new millennium. Upon the recommendation of the International Working Group on Water Reactor Fuel Performance and Technology, water chemistry and corrosion of cladding and primary circuit components are in the focus of the IAEA activities in the area of fuel technology and performance. At present the IAEA performs two co-ordinated research projects (CRPs): on On-line High Temperature Monitoring of Water Chemistry and Corrosion (WACOL) and on Activity Transport in Primary Circuits. Two CRPs deal with hydrogen and hydride degradation of the Zr-based alloys. A state-of-the-art review entitled: 'Waterside Corrosion of Zirconium Alloys in Nuclear Power Plants' was published in 1998. Technical Committee meetings on the subject were held in 1985 (Cadarache, France), 1989 (Portland, USA), 1993 (Rez, Czech Republic). During the last few years extensive exchange of experience in

  3. Nuclear fuel behaviour modelling at high burnup and its experimental support. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2001-07-01

    The Technical Committee Meeting (TCM) included separate sessions on the specific topics of fuel thermal performance and fission product retention. On thermal performance, it is apparent that the capability exists to measure conductivity in high burnup fuel either by out-of-pile measurement or by instrumentation of test reactor rods. State-of-the-art modelling codes contain models for the conductivity degradation process, and hence adequate predictions of fuel temperature are achievable. Concerning fission product release, it is clear that many groups around the world are actively investigating the subject, with experimental and modelling programmes being pursued. However, a general consensus on the exact mechanisms of gas release and related gas bubble swelling has yet to emerge, even at medium burnup levels. Fission gas phenomena, not only the release to open volumes, but the whole sequence of processes taking place prior to this, need to be modelled in any modern fuel performance code. The presence of gaseous fission products may generate rapid fuel swelling during power transients, and this can cause PCI and rod failure. At high burnups, the quantity of released gases could give rise to pressures exceeding the safe limits. Modelling of pellet-cladding interaction (PCI) effects during transient operation is also an active area of study for many groups. In some situations a purely empirical approach to failure modelling can be justified, while for other applications a more detailed mechanistic approach is required. Another aspect of cladding modelling which was featured at the TCM concerned corrosion and hydriding. Although this issue can be the main life-limiting factor on fuel duty, it is apparent that modelling methods, and the experimental measurement techniques that underpin them, are adequate. A session was included on MOX fuel modelling. Substantial programmes of work, especially by the MOX vendors, appear to be underway to bring the level of understanding

  4. Influence of water chemistry on fuel cladding behaviour. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-02-01

    For the purpose of the meeting water chemistry included the actual practice, the water chemistry monitoring and the on-going research. Corrosion included also hydriding, recent observations made in reactors, modelling and the recent research carried out. Fifty seven participants representing twenty countries attended the thirty formal presentations and the subsequent discussions. The thirty papers presented were split into five sessions covering, Reactor experience, Mechanism and Modelling, Oxidation and hydriding, On-line monitoring of water chemistry and the review of existing and advanced water chemistries. Four panel discussions including ''Corrosion mechanism and Modelling'', ''Corrosion and Hydriding'', ''Plant Experience and Loop Experiments'', Water Chemistry, Current Practice and Emerging Solutions'' and ''On-line Monitoring of Water Chemistry and Corrosion'' were organized. The main points of discussion focussed on the optimization of water chemistry, the compatibility of potassium water chemistry with the utilization of Zircaloy 4 or the utilization of zirconium niobium cladding with lithium water chemistry. The effect of the fabrication route and of the cladding composition (Sn content) on the corrosion kinetics, the state of the art and the correlative gaps in cladding corrosion modelling and the recent developments of on-line monitoring of water chemistry together with examination of suitable developments, were also discussed. Refs, figs, tabs

  5. 75 FR 60466 - Center for Scientific Review; Notice of Closed Meetings

    Science.gov (United States)

    2010-09-30

    ... Health, 6701 Rockledge Drive, Bethesda, MD 20892. (Virtual Meeting) Contact Person: Jane A Doussard.... (Virtual Meeting) Contact Person: Peter J. Perrin, PhD, Scientific Review Officer, Center for Scientific...

  6. IAEA Technical Meeting on Status of IAEA Fast Reactor Knowledge Preservation Initiative. Working Material

    International Nuclear Information System (INIS)

    2013-01-01

    In response to needs expressed by Member States and within a broader IAEA-wide effort in nuclear knowledge preservation, the IAEA has been carrying out a dedicated initiative on Fast Reactor Data Knowledge Preservation (FRKP). The main objectives of the FRKP initiative are to: • Halt the on-going loss of information related to Fast Reactors (FR); • Collect, retrieve, preserve and make accessible already existing data and information on FR. These objectives require the implementation of activities supporting digital document archival, exchange, search and retrieval and facilitating, by developing and using suitable standards and IT tools, the knowledge preservation over the next decades. To this purpose the IAEA has developed the Fast Reactor Knowledge Organization System (FRKOS), a web-based application employing IAEA methodology and approach for categorization of FR knowledge domain, which allows creating a comprehensive and well-structured international inventory of fast reactor data and information provided by different Member States. The resulting Web Portal is established and maintained by the IAEA. The IAEA knowledge preservation initiatives and tools in the field of fast neutron systems - which were presented and very well received during the recent IAEA Fast Reactor and Related Fuel Cycles Conference (FR13) - are supposed to be of interest for national nuclear authorities, regulators, scientific and research organizations, commercial companies and all other stakeholders involved in fast reactor activities at national or international level. The objectives of the technical meeting were to: • Exchange information between the member states/international organizations on national and international initiatives addressing knowledge preservation and data retrieval/collection in the field of fast neutron systems; • Present and discuss the member states’/international organizations’ policies and conditions for releasing to the IAEA both publicly

  7. Proceedings of the fuel cells 1994 contractors review meeting

    Science.gov (United States)

    Carpenter, C. P., II; Mayfield, M. J.

    1994-08-01

    METC annually sponsors this conference to provide a forum for energy executives, engineers, etc. to discuss advances in fuel cell research and development projects, to exchange ideas with private sector attendees, and to review relevant results in fuel cell technology programs. Two hundred and three people from industry, academia, and Government attended. The conference attempts to showcase the partnerships with the Government and with industry, by seeking activity participation and involvement from the Office of Energy Efficiency and Renewable Energy, EPRI, GRI, and APRA. In addition to sessions on fuel cells (solid oxide, molten carbonate, etc.) for stationary electric power generation, sessions on US DOE's Fuel Cell Transportation Program and on DOD/APRA's fuel cell logistic fuel program were presented. In addition to the 29 technical papers, an abstract of an overview of international fuel cell development and commercialization plans in Europe and Japan is included. Selected papers were indexed separately for inclusion in the Energy Science and Technology Database.

  8. Tech Writing, Meet "Tomb Raider": Video and Computer Games in the Technical Communication Classroom

    Science.gov (United States)

    Vie, Stephanie

    2008-01-01

    This article examines the common genre of the usability study in technical communication courses and proposes the incorporation of computer and video games to ensure a rhetorical focus to this genre. As games are both entertaining and educational, their use in the technical communication classroom provides a new perspective on multimodal…

  9. Commercial products and services of research reactors. Proceedings of a technical meeting held in Vienna 28 June - 2 July 2010

    International Nuclear Information System (INIS)

    2013-07-01

    Although the number of operational research reactors is steadily decreasing, more than half of those that remain are greatly underutilized and, in most cases, underfunded. To continue to play a key role in the development of peaceful uses of nuclear technology, the remaining research reactors will need to provide useful products and services to private, national and regional customers, in some cases with adequate revenue generation for reliable, safe and secure facility management and operation. In the light of declining governmental financial support and the need for improved physical security and conversion to low enriched uranium (LEU) fuel, many research reactors have been challenged to generate income to offset increasing operational and maintenance costs. The renewed interest in nuclear power (and therefore in nuclear education and training), the global expansion of diagnostic and therapeutic nuclear medicine, and the extensive use of semiconductors in electronics and in other areas have created new opportunities for research reactors, prominent among them, markets for products and services in regions and countries without such facilities. It is clear that such initiatives towards greater self-reliance will need to address such aspects as market surveys, marketing and business plans, and cost of delivery services. It will also be important to better inform present and future potential end users of research reactor services of the capabilities and products that can be provided. This publication is a compilation of material from an IAEA technical meeting on 'Commercial Products and Services of Research Reactors', held in Vienna, Austria, from 28 June to 2 July 2010. The overall objective of the meeting was to exchange information on good practices and to provide concrete examples, in technical presentations and brainstorming discussions, to promote and facilitate the development of commercial applications of research reactors. The meeting also aimed to enhance

  10. SUPPLEMENTAL COLUMBIA RIVER PROTECTION ACTIVITIES AT THE DEPARTMENT OF ENERGY HANFORD SITE 2008 TECHNICAL REVIEW

    Energy Technology Data Exchange (ETDEWEB)

    Looney, B; Dawn S. Kaback, D; Eugene L. LeBoeuf, E; Joe Rossabi, J; Karen L. Skubal, K; David L. Cocke, D; Paul C. Deutsch, P

    2008-09-30

    Beginning in 2006, the US Department of Energy (DOE) supported nine applied research projects to improve the protection of the Columbia River and mitigate the impacts of Hanford Site groundwater. These projects were funded through a supplemental Congressional budget allocation, and are now in various stages of completion in accordance with the research plans. The DOE Office of Environmental Management Groundwater and Soil Cleanup Technologies (EM-22) sponsored a technical peer review meeting for these projects in Richland WA, July 28-31, 2008. The overall objective of the peer review is to provide information to support DOE decisions about the status and potential future application of the various technologies. The charge for the peer review panel was to develop recommendations for each of the nine 'technologies'. Team members for the July 2008 review were Brian Looney, Gene LeBoeuf, Dawn Kaback, Karen Skubal, Joe Rossabi, Paul Deutsch, and David Cocke. Previous project reviews were held in May 2007 and March-May of 2006. The team used the following four rating categories for projects: (a) Incorporate the technology/strategy in ongoing and future EM activities; (b) Finish existing scope of applied research and determine potential for EM activities when research program is finished; (c) Discontinue current development activities and do not incorporate technology/strategy into ongoing and future EM activities unless a significant and compelling change in potential viability is documented; and (d) Supplement original funded work to obtain the data needed to support a DOE decision to incorporate the technology into ongoing and future EM activities. The supplemental funding portfolio included two projects that addressed strontium, five projects that addressed chromium, one project that addressed uranium and one project that addressed carbon tetrachloride. The projects ranged from in situ treatment methods for immobilizing contaminants using chemical

  11. Proceedings of the Fuel Cells `97 Review Meeting

    Energy Technology Data Exchange (ETDEWEB)

    None

    1998-01-01

    The Federal Energy Technology Center (FETC) sponsored the Fuel Cells '97 Review Meeting on August 26-28, 1997, in Morgantown, West Virginia. The purpose of the meeting was to provide an annual forum for the exchange of ideas and discussion of results and plans related to the research on fuel cell power systems. The total of almost 250 conference participants included engineers and scientists representing utilities, academia, and government from the U.S. and eleven other countries: Canada, China, India, Iran, Italy, Japan, Korea, Netherlands, Russia, Taiwan, and the United Kingdom. On first day, the conference covered the perspectives of sponsors and end users, and the progress reports of fuel-cell developers. Papers covered phosphoric, carbonate, and solid oxide fuel cells for stationary power applications. On the second day, the conference covered advanced research in solid oxide and other fuel cell developments. On the third day, the conference sponsored a workshop on advanced research and technology development. A panel presentation was given on fuel cell opportunities. Breakout sessions with group discussions followed this with fuel cell developers, gas turbine vendors, and consultants.

  12. 77 FR 14533 - Center for Scientific Review: Notice of Closed Meetings

    Science.gov (United States)

    2012-03-12

    ...: Shared Instrument Review. Date: March 21-22, 2012. Time: 8 a.m. to 5 p.m. Agenda: To review and evaluate..., (Virtual Meeting). Contact Person: Ping Fan, MD, Ph.D., Scientific Review Officer, Center for Scientific.... Place: National Institutes of Health, 6701 Rockledge Drive, Bethesda, MD 20892, (Virtual Meeting...

  13. 77 FR 18268 - Proposal Review Panel for Engineering Education and Centers; Notice of Meeting

    Science.gov (United States)

    2012-03-27

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Engineering Education and Centers; Notice of... Science Foundation announces the following meeting: Name: Proposal Review Panel for Engineering Education... Meeting: NSF site visit to conduct a renewal review during year 6 of the award period as stipulated in the...

  14. The Ins and Outs of Viral Infection: Keystone Meeting Review

    Directory of Open Access Journals (Sweden)

    Sara W. Bird

    2014-09-01

    Full Text Available Newly observed mechanisms for viral entry, assembly, and exit are challenging our current understanding of the replication cycle of different viruses. To address and better understand these mechanisms, a Keystone Symposium was organized in the snowy mountains of Colorado (“The Ins and Outs of Viral Infection: Entry, Assembly, Exit, and Spread”; 30 March–4 April 2014, Beaver Run Resort, Breckenridge, Colorado, organized by Karla Kirkegaard, Mavis Agbandje-McKenna, and Eric O. Freed. The meeting served to bring together cell biologists, structural biologists, geneticists, and scientists expert in viral pathogenesis to discuss emerging mechanisms of viral ins and outs. The conference was organized around different phases of the viral replication cycle, including cell entry, viral assembly and post-assembly maturation, virus structure, cell exit, and virus spread. This review aims to highlight important topics and themes that emerged during the conference.

  15. 75 FR 61228 - Board Meeting: Technical Lessons Gained From High-Level Nuclear Waste Disposal Efforts

    Science.gov (United States)

    2010-10-04

    ... Nuclear Waste Disposal Efforts Pursuant to its authority under section 5051 of Public Law 100-203, Nuclear... the hotel for meeting attendees. To ensure receiving the meeting rate, reservations must be made by October 6, 2010. For directions to the hotel or to make reservations, go to http://www.marriott.com/hotels...

  16. 77 FR 65857 - Materials Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-10-31

    ..., first serve basis. To join the conference, submit inquiries to Ms. Yvette Springer at Yvette.Springer... Committee members, the materials should be forwarded prior to the meeting to Ms. Springer via email. The... meeting will be open to the public. For more information, call Yvette Springer at (202) 482-2813. Dated...

  17. 18th 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, B.J.

    2013-12-01

    The 18th meeting of the Subcommittee on Atomic and Molecular Data of the International Fusion Research Council (IFRC) was held on 26-27 April 2012 at IAEA Headquarters in Vienna, Austria. Activities of the Atomic and Molecular Data Unit for the period 2010-2012 were reviewed and recommendations were made for continuig activitiees in 2012-2013 and for new projects in the 2014-2015 budget cycle. The proceedings, conclusions and recommendations of the Subcommittee meeting are briefly described in this report. Specific recommendations of the Subcommittee from this meeting, as well as the report on the activities of the IAEA Atomic and Molecular Data Unit for the period May 2010 - April 2012, are also included. (author)

  18. Application and development of probabilistic safety assessment for nuclear power plant operations. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1996-04-01

    The Technical Committee Meeting on Procedures for Use of PSA for Optimizing Operational Limits and Conditions for Nuclear Power Plants was held in Barcelona from 20 to 23 September 1993 to serve as a forum for discussion of the development of methods and approaches for PSA applications. The meeting was co-sponsored by the IAEA and the Asco and Vandellos nuclear power plants in Spain and was attended by more than 85 participants from 23 countries. The 35 papers and presentations reflected the extent of activities in this area worldwide. Most of the papers discuss PSA application programmes and/or specific methods and approaches used. This TECDOC, which was prepared by the participants of the Technical Committee meeting, summarizes the insights gained from the papers and plenary discussions. It also presents the conclusions of the work of three working groups which discussed the advantages and limitations of specific aspects of PSA. It provides an up-to-date description of computerized tools for risk monitoring in used or under development in Member States. It is hoped that this report will be a useful source of information on PSA applications. Refs, figs, tabs

  19. Review and comment on the advanced spent fuel management process (1): Technical aspects and non-proliferation concerns

    Energy Technology Data Exchange (ETDEWEB)

    Song, Yo Taik

    2001-01-01

    Efforts are made to analyze the project, the Advanced Spent Fuel Management Technology (ASFMT), which is currently carried out at Korea Atomic Energy Research Institute, on the technical feasibility and validity as well as on the nuclear non-proliferation concerns. The project is a part of a program under the 'Long and Midterm Nuclear Development Program'. On the technical analysis, reviewed the papers presented at the national and international meetings on the subject by KAERI staffs, and also participated to various technical discussions on the 'Mock-up Test', currently in progress. On the non-proliferation concerns, the ASFMT project was reviewed and analyzed in reference to various programs currently in progress or in a formulation stages in US, such as the DOE TOPS and ATW. Further reviewed the past JASNEC process and programs for possible application of the ASFMT project for JASNEC project. Provided a few thoughts for effectively carrying out the ASFMT project, and a plan for the next phase is presented.

  20. Review and comment on the advanced spent fuel management process (1): Technical aspects and non-proliferation concerns

    International Nuclear Information System (INIS)

    Song, Yo Taik

    2001-01-01

    Efforts are made to analyze the project, the Advanced Spent Fuel Management Technology (ASFMT), which is currently carried out at Korea Atomic Energy Research Institute, on the technical feasibility and validity as well as on the nuclear non-proliferation concerns. The project is a part of a program under the 'Long and Midterm Nuclear Development Program'. On the technical analysis, reviewed the papers presented at the national and international meetings on the subject by KAERI staffs, and also participated to various technical discussions on the 'Mock-up Test', currently in progress. On the non-proliferation concerns, the ASFMT project was reviewed and analyzed in reference to various programs currently in progress or in a formulation stages in US, such as the DOE TOPS and ATW. Further reviewed the past JASNEC process and programs for possible application of the ASFMT project for JASNEC project. Provided a few thoughts for effectively carrying out the ASFMT project, and a plan for the next phase is presented

  1. Factors that affect scrub practitioner non-technical skills: A literature review.

    Science.gov (United States)

    McClelland, Guy

    2018-04-01

    Non-technical skills are the cognitive and interpersonal behaviours that compliment clinical competence in surgery. Effective use of non-technical skills is essential for scrub practice, because they facilitate anticipation of the surgeon's requirements and promote appropriate communication behaviours. This literature review analyses the factors that may influence a scrub practitioner's use of non-technical skills during surgery. Recommendations are made that are intended to improve their use by reducing behavioural variations during surgery.

  2. 78 FR 12422 - Health Services Research and Development Service Scientific Merit Review Board, Notice of Meeting

    Science.gov (United States)

    2013-02-22

    ... DEPARTMENT OF VETERANS AFFAIRS Health Services Research and Development Service Scientific Merit... nursing research. Applications are reviewed for scientific and technical merit, mission relevance, and the... Program Manager, Scientific Merit Review Board, Department of Veterans Affairs, Health Services Research...

  3. Minutes of Technical Division Steering Committee Meeting, September 13, 1955 -- Savannah River Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Evans, L.C.

    1955-09-16

    The Steering Committee approved 8 studies related to separation processes, analytical chemistry, waste handling, and recycle development. Safety and security issues were discussed. Appendices detail the financial status of the Technical Division and estimated man months for development studies approved for the Purex Process, tritium separations, thorium recycle, U-235 separations, and 100-, 200-, and 300-Area studies in analytical chemistry development. The status of 25 other Technical Division studies are listed along with their budget.

  4. Utilization of a Technical Peer Review to Support the Mission of the Nevada Test Site Community Advisory Board

    International Nuclear Information System (INIS)

    Dixon, Earle C.; Peterson, Kathleen

    2003-01-01

    The U. S. Department of Energy's (DOE) National Nuclear Security Administration Nevada Operations Office (NNSA/NV) Environmental Management (EM) Underground Test Area (UGTA) project addresses the characterization and needs for long-term monitoring of the subsurface contamination resulting from 828 underground nuclear weapon tests at the Nevada Test Site (NTS). EM promotes, and is required, to include stakeholders in its program. However, UGTA is a very complex program not easily understood by members of the public. The NTS Community Advisory Board (CAB), a federally chartered Site Specific Advisory Board (SSAB), has studied the UGTA project since 1996, and has found it a challenge to completely comprehend and provide NNSA/NV meaningful citizen input. The CAB realized the benefit of a technical peer review and in 2000 recommended to NNSA/NV that a peer review of the UGTA strategy would provide valuable feedback to the program to address underground contamination at the NTS. N NSA agreed to the CAB's recommendation, and moved forward with a scope of work to have the American Society of Mechanical Engineers (ASME) perform the peer review of the UGTA strategy. The ASME began the peer review in June 2001, and their final report was published in November 2001. In January 2002, the CAB devoted their monthly meeting in Las Vegas, Nevada to reporting the results of the peer review of the UGTA strategy to the public. Two public workshops were later held in the community of Amargosa, Nevada during the month of January to help educate and build interest in the CAB February 2002 monthly meeting which was also held in Amargosa. The CAB recommendation to NNSA to utilize a technical peer review has provided valuable information to NNSA, the State of Nevada, and the CAB. At other DOE sites SSABs are challenged by a number of complex, technical programs requiring considerable time and resources for the board to comprehend. It is worth considering the utilization of an independent

  5. Proceedings of the Annual Meeting of the Council for Programs in Technical and Scientific Communication (14th, Orlando, Florida, October 7-9, 1987).

    Science.gov (United States)

    Geonetta, Sam C., Ed.

    Based on the notion of "reaching out," this proceedings presents papers from the annual meeting of the Council for Programs in Technical and Scientific Communication. Papers in the proceedings are: "Southern Tech's Technical Writing Certificate" (William S. Pfeiffer); "Reach Out and Quack Someone" (Daniel R. Jones);…

  6. Summary Report of the Technical Meeting on Long-term Needs for Nuclear Data Development

    International Nuclear Information System (INIS)

    Plompen, A.

    2012-01-01

    The Advisory Group Meeting on Long Term Needs for Nuclear Data Development was held from 2 - 4 November 2011 at IAEA Headquarters, Vienna, Austria. The goal of this meeting was to develop a vision of the work needed over the next decade (2012-2022) on the measurement, calculation and evaluation of improved nuclear data for various applications. Of particular interest were data improvement activities that could be coordinated by the IAEA. The following areas of nuclear data applications were selected for discussion during the Meeting: Medical and Analytical Applications; Energy Production; Data libraries; Basic Science and Tools/Visualisation. (author)

  7. Developing a programme on molecular nuclear medicine. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2007-07-01

    been increasingly applied for revealing the different profiles of normal and affected cells or tissues and also for the following-up treatment of certain diseases like minimal residual disease (MRD). The detection of changes in the level of transcription of certain genes using this approach has been a useful tool for the early detection of disease, improving the patient survival. At the Technical Meeting on Developing a Medium to Long Term Programme on Molecular Nuclear Medicine, held in Vienna, 29 November - 1 December 2004, certain areas were selected as the best candidates to be included in the IAEA's programme in relation to their applicability and potential to improve human health. The IAEA will continue supporting training activities and fellowships, and encouraging developing Member States to take advantage of the use of isotopic advanced molecular techniques for the resolution of their health problems. This TECDOC contains useful information for health workers in the nuclear medicine and molecular biology fields. Previous IAEA publications, Nuclear Medicine Resources Manual (STI/PUB/1198), Radionuclides in Molecular Technology for Diagnosis of Communicable Diseases (IAEA-TECDOC-748), In Vitro Radionuclide Techniques in Medical Diagnosis (IAEA-TECDOC-1001) and Organization of a Radioisotope Based Molecular Biology Laboratory (IAEA-TECDOC-1528), are separately focused on nuclear medicine and molecular biology techniques applied to human diseases, while the present publication provides presentations on the advances of molecular nuclear medicine techniques

  8. Low cost options for tissue culture technology in developing countries. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2004-02-01

    low cost options, and increasing plant survival after propagation, bioreactors, and outreach of material to the growers and farmers in developing countries. Bioreactors in plant propagation can produce millions of plants and may cut down the cost of plant production, which is yet not commonly used in developing countries. However, in the near future it could be well integrated into large scale commercial micropropagation in both developed and developing countries. In all cases, such options must be integrated without reducing the efficiency of plant propagation and compromising the plant quality. This TECDOC was prepared on the basis of contributions made by the participants in the Technical Meeting on Low Cost Tissue Culture Technology for Developing Countries, Vienna, 26-30 August 2002. This publication should be of great value to plant propagators, managers of tissue culture laboratories, scientists, organizations contemplating the establishment of new laboratories, and ongoing commercial concerns, all of whom may wish to incorporate low cost options into their day-to-day operations. Also, it would greatly serve plant propagation enterprises in developing countries with scarce funds and poor infrastructure for sustainable food production. Many of the options described can also be integrated in tissue culture laboratories that use mutation induction to develop new mutant varieties of both vegetatively and seed propagated plants, and for rapid release of the selected mutants

  9. Technical committee meeting on material-coolant interactions and material movement and relocation in liquid metal fast reactors

    International Nuclear Information System (INIS)

    1994-01-01

    The Technical Committee Meeting on Material-Coolant Interactions and Material Movement and Relocation in Liquid Metal Fast Reactors was sponsored by the International Working Group on Fast Reactors (IWGFR), International Atomic Energy Agency (IAEA) and hosted by PNC, on behalf of the Japanese government. A broad range of technical subjects was discussed in the TCM, covering entire aspects of material motion and interactions relevant to the safety of LMFRs. Recent achievement and current status in research and development in this area were presented including European out-of-pile test of molten material movement and relocation; molten material-sodium interaction; molten fuel-coolant interaction; core disruptive accidents; sodium boiling; post accident material relocation, heat removal and relevant experiments already performed or planned

  10. Review of PREPA Technical Requirements for Interconnecting Wind and Solar Generation

    Energy Technology Data Exchange (ETDEWEB)

    Gevorgian, Vahan [National Renewable Energy Lab. (NREL), Golden, CO (United States); Booth, Sarah [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2013-11-01

    The Puerto Rico Electric Power Authority developed the minimum technical requirements for interconnection of wind turbine generation and photovoltaic power plants. NREL has conducted a review of these requirements based on generic technical aspects and electrical characteristics of wind and photovoltaic power plants, and on existing requirements from other utilities (both U.S. and European).

  11. In-core fuel management: Reloading techniques. Proceedings of a technical committee meeting and workshop held in Vienna, 19-21 October 1992

    International Nuclear Information System (INIS)

    1995-08-01

    The purpose of the Technical Committee Meeting and Workshop on In-core Fuel Management - Reloading Techniques, convened by the IAEA in Vienna from 19 to 21 October 1992, was to provide an international forum to review and discuss in-core fuel management reloading techniques for light water reactors. A presentation of the history and status of reloading techniques was given by S.H. Levine, Pennsylvania State University, and papers on various computer code descriptions, methodologies and experiences of utilities and vendors for nuclear fuel reloading were presented and discussed. Optimization techniques for reloadings, expert system codes and the number of energy groups used in reloading calculations were discussed in more detail during a workshop session. Refs, figs and tabs

  12. Book Review: Space Research at the Technical University of Moldova.

    Science.gov (United States)

    Gaina, Alex

    Recently the historian of the Technical University of Moldova Aurel Marinchuk (Marinciuc) in a collaboration with the editorial team from the same University has published a Jubiliary Album "50 Years of the Technical University of Moldova". The Album is published at the Technical University in Chisinau (The Republic of Moldova). Two chapters of this album present major interest: 1) Space research at the Technical University of Moldova 2) The Foucault Pendulum manufactured at the same University under the supervision of the Rector of University, Dr. Hab. of Technical Sciences and Member of the Academy of Sciences of the Republic of Moldova Ion Bostan. The parameters of the Pendulums are: m=102 kg L=17,24 m T=8.35 sec. >From the first chapter We learn that 3 astronauts: Frank Lee Culbertson, Vladimir Dezhurov and Dumitru Dorin Prunariu are Doctors Honoris Causa of this University. As well we can found in the album informations about the Microsatellit "Republic of Moldova" built also by a team from the same University. It is ready to fly, but many depends on the funds for launch the Satellite. The Foucault Pendulum presents also interest in view of its possible applications to detect the influence of the relative position of the Sun and the Moon on Earthquakes. As is well known the tidal gravitational Force varies, depending on the relative position of the Sun and the Moon.

  13. Proceedings of the Canadian Society for Bioengineering CSBE/SCGAB 2009 annual general meeting and technical conference

    International Nuclear Information System (INIS)

    2009-01-01

    This conference was attended by experts on current issues in engineering of an urban ecosystem, composting, biofuels and green energy. The meeting provided a forum to discuss advances in the application of engineering principles and practices dealing with biological systems for the production of food, bioproducts and energy. The discussions focused on engineering practices in agriculture, forestry, bioresources, biochemistry and biosystems. The 7 technical sessions of the conference were entitled: aquaculture; safety and training; bioprocessing; energy production and biofuels; environment and ecology; soil and water; and development of technologies. The conference feature 58 presentations, of which 9 have been catalogued separately for inclusion in this database. refs., tabs., figs

  14. Water channel reactor fuels and fuel channels: Design, performance, research and development. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1998-01-01

    The International Working Group on Water Reactor Fuel Performance and Technology (IWGFPT) recommended holding a Technical Committee Meeting on Water Channel Reactor Fuel including into this category fuels and pressure tubes/fuel channels for Atucha-I and II, BWR, CANDU, FUGEN and RBMK reactors. The IWGFPT considered that even if the characteristics of Atucha, CANDUs, BWRs, FUGEN and RBMKs differ considerably, there are also common features. These features include materials aspects, as well as core, fuel assembly and fuel rod design, and some safety issues. There is also some similarity in fuel power history and operating conditions (Atucha-I and II, FUGEN and RBMK). Experts from 11 countries participated at the meeting and presented papers on technology, performance, safety and design, and materials aspects of fuels and pressure tubes/fuel channels for the above types of water channel reactors

  15. 78 FR 66354 - Warm Springs Irrigation District; Notice of Technical Meeting

    Science.gov (United States)

    2013-11-05

    ... Stanleya confertiflora requested by the U.S. Bureau of Land Management on June 7, 2013; the coordination of... project. f. Proposed Agenda: 1. Introduction 2. Meeting objectives 3. Plant survey discussion 4. NEPA...

  16. Technical Review Guidelines for Environmental Impact Assessments in the Tourism, Energy and Mining Sectors

    Science.gov (United States)

    EPA coordinated a regional collaborative process with Central America and Dominican Republic Free Trade Agreement (CAFTA-DR) partners to develop Environmental Impact Assessment (EIA) Technical Review Guidelines for three sectors.

  17. Human Research Program 2010 Chair Standing Review Panel Meeting

    Science.gov (United States)

    Steinberg, Susan

    2011-01-01

    The 13 Human Research Program (HRP) Standing Review Panel (SRP) Chairs, and in some cases one or two additional panel members (see section XIV, roster) referred to as the Chair (+1) SRP throughout this document, met at the NASA Johnson Space Center (JSC) on December 7, 2010 to allow the HRP Elements and Projects to report on their progress over the past year, their current status, and their plans for the upcoming year based on NASA's current goals and objectives for human space exploration. A large focus of the meeting was also used to discuss integration across the HRP scientific disciplines based on a recommendation from the 2009 HRP SRP review. During the one-day meeting, each of the HRP Elements and Projects presented the changes they made to the HRP Integrated Research Plan (IRP Rev. B) over the last year, and what their top three areas of integration are between other HRP Elements/Projects. The Chair (+1) SRP spent sufficient time addressing the panel charge, either as a group or in a separate closed session, and the Chair (+1) SRP and the HRP presenters and observers, in most cases, had sufficient time to discuss during and after the presentations. The SRP made a final debriefing to the HRP Program Scientist, Dr. John B. Charles, prior to the close of the meeting on December 7, 2010. Overall, the Chair (+1) SRP concluded that most of the HRP Elements/Projects did a commendable job during the past year in addressing integration across the HRP scientific disciplines with the available resources. The Chair (+1) SRP agreed that the idea of integration between HRP Elements/Projects is noble, but believes all parties involved should have the same definition of integration, in order to be successful. The Chair (+1) SRP also believes that a key to successful integration is communication among the HRP Elements/Projects which may present a challenge. The Chair (+1) SRP recommends that the HRP have a workshop on program integration (with HRP Element

  18. 76 FR 63314 - Center for Scientific Review Notice of Closed Meetings

    Science.gov (United States)

    2011-10-12

    ... U.S.C. App.), notice is hereby given of the following meetings. The meetings will be closed to the public in accordance with the provisions set forth in sections 552b(c)(4) and 552b(c)(6), Title 5 U.S.C..., (Virtual Meeting). Contact Person: Yi-Hsin Liu, PhD, Scientific Review Officer, Center for Scientific...

  19. Recent developments in post-irradiation examination techniques for water reactor fuel. Proceedings of a technical committee meeting held in Cadarache, France, 17-21 October 1994

    International Nuclear Information System (INIS)

    1995-09-01

    At the invitation of the Government of France, following a proposal of the International Working Group on Water Reactor Fuel Performance and Technology (IWGFPT) the IAEA convened a Technical Committee meeting from 14 to 21 October 1994 in Cadarache to discuss recent technical advances and improvements in the field of post-irradiation examination (PIE) of fuel used in nuclear power plants. Fifty participants representing 14 countries attended the meeting and 30 papers were presented and discussed during five technical sessions. Working Groups composed of the session chairmen and authors of papers prepared summaries of each session including conclusions and recommendations for future work. Refs, figs and tabs

  20. Technical meeting on development of 'Deep Burn' concepts using coated particle fuel for incineration of nuclear waste, surplus fissile materials and plutonium without recourse to multiple reprocessing. Meeting report

    International Nuclear Information System (INIS)

    2013-01-01

    Summary report of the technical meeting. The purpose of this meeting is to explore various Deep-Burn options and concepts being developed in Member States and to appraise the progress made towards the maturity of Deep-Burn concepts based on HTGR designs. The meeting will also identify technology development challenges towards the realization of Deep-Burn concepts and propose collaborative ways to address them

  1. 78 FR 4464 - Proposal Review Panel for Materials Research; Notice of Meeting

    Science.gov (United States)

    2013-01-22

    ..., Draft and Review Site visit report Reason for Closing: The work being reviewed may include information... of Meeting: To provide advice and recommendations concerning the progress of ERL technology...

  2. [Classification and review of technical devices for hypoxia therapy].

    Science.gov (United States)

    Lopata, V O; Berezovs'kyĭ, V Ia; Levashov, M I; Kyienko, V M

    2003-01-01

    In the report there considered and compared the functional and constructive features of hipoxicators, divided in classification groups. The complex of medico-technical requirements to hipoxicators is formulated; prospects of perfection of therapeutic and diagnostic methods for hypoxitherapy and their hardware are estimated.

  3. VOCATIONAL-TECHNICAL EDUCATION IN NIGERIA: A REVIEW

    African Journals Online (AJOL)

    DJFLEX

    2009-08-17

    Aug 17, 2009 ... Vocational-technical education (VTE) is defined as that aspect of education which leads to the .... The college was to engage in professional and sub- professional training in the following programmes: (a) Teachers training for trade schools and junior ..... achieved economic aims because investment in.

  4. Proceedings of the fuel cells `94 contractors review meeting

    Energy Technology Data Exchange (ETDEWEB)

    Carpenter, C.P. II; Mayfield, M.J. [eds.] [USDOE Morgantown Energy Technology Center, WV (United States)

    1994-08-01

    METC annually sponsors this conference to provide a forum for energy executives, engineers, etc. to discuss advances in fuel cell research and development projects, to exchange ideas with private sector attendees, and to review relevant results in fuel cell technology programs. Two hundred and three people from industry, academia, and Government attended. The conference attempts to showcase the partnerships with the Government and with industry, by seeking activity participation and involvement from the Office of Energy Efficiency and Renewable Energy, EPRI, GRI, and APRA. In addition to sessions on fuel cells (solid oxide, molten carbonate, etc.) for stationary electric power generation, sessions on US DOE`s Fuel Cell Transporation Program and on DOD/APRA`s fuel cell logistic fuel program were presented. In addition to the 29 technical papers, an abstract of an overview of international fuel cell development and commercialization plans in Europe and Japan is included. Selected papers were indexed separately for inclusion in the Energy Science and Technology Database.

  5. 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)

  6. 78 FR 65265 - Materials Technical Advisory Committee; Notice of Open Meeting

    Science.gov (United States)

    2013-10-31

    ... BIS senior management and export control reform update. 3. Presentation from DuPont on the challenges... NW., Washington, DC. The Committee advises the Office of the Assistant Secretary for Export Administration with respect to technical questions that affect the level of export controls applicable to...

  7. 78 FR 20100 - Public Utility District No. 1 of Snohomish County, WA; Notice of Technical Meeting

    Science.gov (United States)

    2013-04-03

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Public Utility District No. 1 of Snohomish County, WA; Notice of Technical... the proposed Admiralty Inlet Pilot Tidal Project included by Public Utility District No. 1 of...

  8. 78 FR 12063 - Meeting for Software Developers on the Technical Specifications for Common Formats for Patient...

    Science.gov (United States)

    2013-02-21

    ... disability is needed, please contact the Food and Drug Administration (FDA) Office of Equal Employment... Medicare & Medicaid Services, Food and Drug Administration, Health Resources and Services Administration... patient safety event data. The technical specifications consist of the following: [cir] Data dictionary...

  9. 77 FR 9252 - Meeting for Software Developers on the Technical Specifications for Common Formats for Patient...

    Science.gov (United States)

    2012-02-16

    ... other reasonable accommodation for a disability is needed, please contact the Food and Drug...)--the Centers for Disease Control and Prevention, Centers for Medicare & Medicaid Services, Food and... technical specifications consist of the following: Data dictionary--defines data elements and their...

  10. Minutes of Technical Division Steering Committee meeting August 9, 1955, Savannah River Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    1955-08-15

    Study approvals are listed for Studies 8506, 8509, 8518, 8519, and 8520 with man-months and program dates specified. Safety and security agreements are listed. Additional topics discussed are: financial status, experimental physics programs, pile engineering division program, and technical division study status.

  11. 75 FR 3942 - Proposal Review Panel for Chemistry; Notice of Meeting

    Science.gov (United States)

    2010-01-25

    ... ``Center for Green Materials Chemistry (CGMC)'' 4-4:30, Closed Discussions (NSF staff, panel, CGMC) 4:30-5... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Chemistry; Notice of Meeting In accordance... announces the following meeting. Name: Centers for Chemical Innovation (CCI) Phase I Cyber Review Panel...

  12. 77 FR 69505 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2012-11-19

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics; Notice of Meeting In accordance with the Federal Advisory Committee Act (Pub. L. 92- 463, as amended), the National Science Foundation announces the following meeting. Name: LIGO Operations Proposal and Annual Review in Physics (1208). Date...

  13. 77 FR 14441 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2012-03-09

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics; Notice of Meeting In accordance... announces the following meeting. Name: LIGO Annual Review Site Visit at Hanford Observatory for Physics...: Partially Closed. Contact Person: Thomas Carruthers, Program Director, Division of Physics, National Science...

  14. 77 FR 5471 - Announcement of Public Meeting on the Consumer Confidence Report (CCR) Rule Retrospective Review

    Science.gov (United States)

    2012-02-03

    ... Announcement of Public Meeting on the Consumer Confidence Report (CCR) Rule Retrospective Review AGENCY... stakeholder input on the Consumer Confidence Report (CCR) Rule as part of the agency's Retrospective Review of... implementing CCR delivery certification, use of CCRs to meet Tier 3 Public Notification requirements, and how...

  15. 76 FR 4113 - Independent Scientific Peer Review Panel Meeting on an In Vitro

    Science.gov (United States)

    2011-01-24

    ... Toxicological Methods (NICEATM); Announcement of an Independent Scientific Peer Review Panel Meeting on an In... DEPARTMENT OF HEALTH AND HUMAN SERVICES Independent Scientific Peer Review Panel Meeting on an In Vitro Estrogen Receptor Transcriptional Activation Test Method for Endocrine Disruptor Chemical...

  16. 77 FR 60116 - Human Studies Review Board; Notification of a Public Meeting

    Science.gov (United States)

    2012-10-02

    ... ENVIRONMENTAL PROTECTION AGENCY [EPA-HQ-ORD-2012-0718; FRL-9736-4] Human Studies Review Board; Notification of a Public Meeting AGENCY: Environmental Protection Agency (EPA). ACTION: Notice. SUMMARY: The EPA Office of the Science Advisor announces a public meeting of the Human Studies Review Board to...

  17. 78 FR 57383 - Human Studies Review Board; Notification of a Public Meeting

    Science.gov (United States)

    2013-09-18

    ... ENVIRONMENTAL PROTECTION AGENCY [EPA-HQ-ORD-2013-0626; FRL-9900-98-ORD] Human Studies Review Board; Notification of a Public Meeting AGENCY: U.S. Environmental Protection Agency (EPA). ACTION: Notice. SUMMARY: The EPA Office of the Science Advisor announces a public meeting of the Human Studies Review Board to...

  18. 77 FR 74004 - Human Studies Review Board; Notification of a Public Meeting

    Science.gov (United States)

    2012-12-12

    ... ENVIRONMENTAL PROTECTION AGENCY [EPA-HQ-ORD-2012-0892; FRL-9761-4] Human Studies Review Board; Notification of a Public Meeting AGENCY: Environmental Protection Agency (EPA). ACTION: Notice. SUMMARY: The EPA Office of the Science Advisor announces a public meeting of the Human Studies Review Board to...

  19. 76 FR 59697 - Human Studies Review Board (HSRB); Notification of a Public Meeting

    Science.gov (United States)

    2011-09-27

    ... public meeting of the Human Studies Review Board (HSRB) to advise the Agency on EPA's scientific and... ENVIRONMENTAL PROTECTION AGENCY [EPA-HQ-ORD-2011-0693; FRL-9472-4] Human Studies Review Board (HSRB); Notification of a Public Meeting AGENCY: Environmental Protection Agency (EPA). ACTION: Notice...

  20. 76 FR 80938 - Human Studies Review Board; Notification of a Public Meeting

    Science.gov (United States)

    2011-12-27

    ... ENVIRONMENTAL PROTECTION AGENCY [EPA-HQ-ORD-2011-0954; FRL-9611-6] Human Studies Review Board; Notification of a Public Meeting AGENCY: U.S. Environmental Protection Agency. ACTION: Notice. SUMMARY: The EPA Office of the Science Advisor announces a public meeting of the Human Studies Review Board to advise the...

  1. 76 FR 17121 - Human Studies Review Board (HSRB); Notification of a Public Meeting

    Science.gov (United States)

    2011-03-28

    ... ENVIRONMENTAL PROTECTION AGENCY [EPA-HQ-ORD-2011-0124; FRL-9287-1] Human Studies Review Board (HSRB); Notification of a Public Meeting AGENCY: Environmental Protection Agency (EPA). ACTION: Notice... public meeting of the HSRB to advise the Agency on EPA's scientific and ethical reviews of research with...

  2. 78 FR 15373 - Center for Scientific Review; Notice of Closed Meeting

    Science.gov (United States)

    2013-03-11

    ....S.C. App.), notice is hereby given of the following meeting. The meeting will be closed to the public in accordance with the provisions set forth in sections 552b(c)(4) and 552b(c)(6), Title 5 U.S.C...). Contact Person: Yi-Hsin Liu, Ph.D., Scientific Review Officer, Center for Scientific Review, National...

  3. 76 FR 36931 - Center for Scientific Review; Notice of Closed Meetings

    Science.gov (United States)

    2011-06-23

    ... U.S.C. App.), notice is hereby given of the following meetings. The meetings will be closed to the public in accordance with the provisions set forth in sections 552b(c)(4) and 552b(c)(6), Title 5 U.S.C...: Yi-Hsin Liu, PhD, Scientific Review Officer, Center for Scientific Review, National Institutes of...

  4. 77 FR 37422 - Center for Scientific Review; Notice of Closed Meetings

    Science.gov (United States)

    2012-06-21

    ... U.S.C. App.), notice is hereby given of the following meetings. The meetings will be closed to the public in accordance with the provisions set forth in sections 552b(c)(4) and 552b(c)(6), Title 5 U.S.C... Liu, Ph.D., Scientific Review Officer, Center for Scientific Review, National Institutes of Health...

  5. 78 FR 64507 - Center for Scientific Review; Notice of Closed Meetings

    Science.gov (United States)

    2013-10-29

    ... U.S.C. App.), notice is hereby given of the following meetings. The meetings will be closed to the public in accordance with the provisions set forth in sections 552b(c)(4) and 552b(c)(6), Title 5 U.S.C...). Contact Person: Yi-Hsin Liu, Ph.D., Scientific Review Officer, Center for Scientific Review, National...

  6. Review of the technical bases of 40 CFR Part 190.

    Energy Technology Data Exchange (ETDEWEB)

    Kelly, John E.; McMahon, Kevin A.; Siegel, Malcolm Dean; Weiner, Ruth F.; Bixler, Nathan E.; Klein, Keith A. (Longenecker and Associates)

    2010-07-01

    The dose limits for emissions from the nuclear fuel cycle were established by the Environmental Protection Agency in 40 CFR Part 190 in 1977. These limits were based on assumptions regarding the growth of nuclear power and the technical capabilities of decontamination systems as well as the then-current knowledge of atmospheric dispersion and the biological effects of ionizing radiation. In the more than thirty years since the adoption of the limits, much has changed with respect to the scale of nuclear energy deployment in the United States and the scientific knowledge associated with modeling health effects from radioactivity release. Sandia National Laboratories conducted a study to examine and understand the methodologies and technical bases of 40 CFR 190 and also to determine if the conclusions of the earlier work would be different today given the current projected growth of nuclear power and the advances in scientific understanding. This report documents the results of that work.

  7. 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

  8. Technical Meeting on Developing Deep-Burn Concepts using HTGRs. Objectives and Expectations

    International Nuclear Information System (INIS)

    Tyobeka, Bismark

    2013-01-01

    The objectives of the meeting are: • To explore various Deep-Burn options and concepts being developed in Member States; • To appraise the progress made towards the maturity of Deep-Burn concepts based on HTGR designs; • To identify technology development challenges towards the realization of Deep-Burn concepts; • To propose collaborative ways to address technology development challenges

  9. 76 FR 72160 - Regulations and Procedures Technical Advisory Committee; Notice of Open Meeting

    Science.gov (United States)

    2011-11-22

    ..., first serve basis. To join the conference, submit inquiries to Ms. Yvette Springer at Yvette.Springer... the meeting to Ms. Springer via email. For more information, call Yvette Springer at (202) 482-2813. Dated: November 16, 2011 Yvette Springer, Committee Liaison Officer. BILLING CODE 3510-JT-P ...

  10. 77 FR 25960 - Materials Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-05-02

    ... Ms. Yvette Springer at Yvette.Springer@bis.doc.gov , no later than May 10, 2012. A limited number of... meeting to Ms. Springer via email. The Assistant Secretary for Administration, with the concurrence of the... information, call Yvette Springer at (202) 482-2813. Dated: April 27, 2012. Yvette Springer, Committee Liaison...

  11. 76 FR 68128 - Materials Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-11-03

    .... Yvette Springer at Yvette.Springer@bis.doc.gov , no later than November 10, 2011. A limited number of... meeting to Ms. Springer via email. The Assistant Secretary for Administration, with the concurrence of the... information, call Yvette Springer at (202) 482-2813. Dated: October 31, 2011. Yvette Springer, Committee...

  12. 77 FR 8807 - Materials Processing Equipment Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-02-15

    ... Springer at Yvette.Springer@bis.doc.gov , no later than March 13, 2012. A limited number of seats will be... materials prior to the meeting to Ms. Springer via email. The Assistant Secretary for Administration, with... information, call Yvette Springer at (202) 482-2813. Dated: February 9, 2012. Yvette Springer, Committee...

  13. 77 FR 65857 - Transportation and Related Equipment Technical Advisory Committee; Notice of Open Meeting

    Science.gov (United States)

    2012-10-31

    ... basis. To join the conference, submit inquiries to Ms. Yvette Springer at Yvette.Springer@bis.doc.gov no... meeting to Ms. Springer via email. For more information, call Yvette Springer at (202) 482 2813. Dated: October 25, 2012. Yvette Springer, Committee Liaison Officer. BILLING CODE P ...

  14. 78 FR 42754 - Materials Processing Equipment Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-07-17

    ... Springer at Yvette.Springer@bis.doc.gov , no later than August 13, 2013. A limited number of seats will be... materials prior to the meeting to Ms. Springer via email. The Assistant Secretary for Administration, with... information, call Yvette Springer at (202) 482-2813. Dated: July 11, 2013. Yvette Springer, Committee Liaison...

  15. 78 FR 63161 - Transportation and Related Equipment Technical Advisory Committee; Notice of Open Meeting

    Science.gov (United States)

    2013-10-23

    ... basis. To join the conference, submit inquiries to Ms. Yvette Springer at Yvette.Springer@bis.doc.gov no... meeting to Ms. Springer via email. For more information, call Yvette Springer at (202) 482-2813. Dated: October 18, 2013. Yvette Springer, Committee Liaison Officer. BILLING CODE P ...

  16. 76 FR 31301 - Regulations and Procedures Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-05-31

    ..., submit inquiries to Ms. Yvette Springer at Yvette.Springer@bis.gov no later than June 7, 2011. A limited... forward the public presentation materials prior to the meeting to Ms. Springer via e-mail. The Assistant... information, call Yvette Springer at (202) 482-2813. Dated: May 23, 2011. Yvette Springer, Committee Liaison...

  17. 78 FR 63161 - Materials Processing Equipment Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-10-23

    ... Springer at Yvette.Springer@bis.doc.gov , no later than October 29, 2013. A limited number of seats will be... materials prior to the meeting to Ms. Springer via email. The Assistant Secretary for Administration, with... more information, call Yvette Springer at (202) 482-2813. Dated: October 18, 2013. Yvette Springer...

  18. 77 FR 42483 - Materials Processing Equipment Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-07-19

    ... Springer at Yvette.Springer@bis.doc.gov , no later than July 31, 2012. A limited number of seats will be... materials prior to the meeting to Ms. Springer via email. The Assistant Secretary for Administration, with... information, call Yvette Springer at (202) 482-2813. Dated: July 13, 2012. Yvette Springer, Committee Liaison...

  19. 77 FR 65857 - Materials Processing Equipment Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-10-31

    ... Springer at Yvette.Springer@bis.doc.gov , no later than November 6, 2012. A limited number of seats will be... materials prior to the meeting to Ms. Springer via email. The Assistant Secretary for Administration, with... more information, call Yvette Springer at (202) 482-2813. Dated: October 24, 2012. Yvette Springer...

  20. 78 FR 24160 - Materials Processing Equipment Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-04-24

    ... Springer at Yvette.Springer@bis.doc.gov , no later than May 7, 2013. A limited number of seats will be... materials prior to the meeting to Ms. Springer via email. The Assistant Secretary for Administration, with... more information, call Yvette Springer at (202) 482-2813. Dated: April 18, 2013. Yvette Springer...

  1. 77 FR 3440 - Materials Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-01-24

    ... Ms. Yvette Springer at Yvette.Springer@bis.doc.gov , no later than February 2, 2012. A limited number... the meeting to Ms. Springer via email. The Assistant Secretary for Administration, with the... public. For more information, call Yvette Springer at (202) 482-2813. Dated: January 19, 2012. Yvette...

  2. Technical review of process heat applications using the HTGR

    International Nuclear Information System (INIS)

    Brierley, G.

    1976-06-01

    The demand for process heat applications is surveyed. Those applications which can be served only by the high temperature gas-cooled reactor (HTGR) are identified and the status of process heat applications in Europe, USA, and Japan in December 1975 is discussed. Technical problems associated with the HTGR for process heat applications are outlined together with an appraisal of the safety considerations involved. (author)

  3. Spatial abilities and technical skills performance in health care: a systematic review.

    Science.gov (United States)

    Langlois, Jean; Bellemare, Christian; Toulouse, Josée; Wells, George A

    2015-11-01

    The aim of this study was to conduct a systematic review and meta-analysis of the relationship between spatial abilities and technical skills performance in health care in beginners and to compare this relationship with those in intermediate and autonomous learners. Search criteria included 'spatial abilities' and 'technical skills'. Keywords related to these criteria were defined. A literature search was conducted to 20 December, 2013 in Scopus (including MEDLINE) and in several databases on EBSCOhost platforms (CINAHL Plus with Full Text, ERIC, Education Source and PsycINFO). Citations were obtained and reviewed by two independent reviewers. Articles related to retained citations were reviewed and a final list of eligible articles was determined. Articles were assessed for quality using the Scottish Intercollegiate Guidelines Network-50 assessment instrument. Data were extracted from articles in a systematic way. Correlations between spatial abilities test scores and technical skills performance were identified. A series of 8289 citations was obtained. Eighty articles were retained and fully reviewed, yielding 36 eligible articles. The systematic review found a tendency for spatial abilities to be negatively correlated with the duration of technical skills and positively correlated with the quality of technical skills performance in beginners and intermediate learners. Pooled correlations of studies were -0.46 (p = 0.03) and -0.38 (95% confidence interval [CI] -0.53 to -0.21) for duration and 0.33 (95% CI 0.20-0.44) and 0.41 (95% CI 0.26-0.54) for quality of technical skills performance in beginners and intermediate learners, respectively. However, correlations between spatial abilities test scores and technical skills performance were not statistically significant in autonomous learners. Spatial abilities are an important factor to consider in selecting and training individuals in technical skills in health care. © 2015 John Wiley & Sons Ltd.

  4. Recent developments in uranium resources and production with emphasis on in situ leach mining. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2004-06-01

    An important role of the International Atomic Energy Agency is establishing contacts between Member States in order to foster the exchange of scientific and technical information on uranium production technologies. In situ leach (ISL) mining is defined as, the extraction of uranium from the host sandstone by chemical solutions and the recovery of uranium at the surface. ISL extraction is conducted by injecting a suitable leach solution into the ore zone below the water table; oxidizing, complexing, and mobilizing the uranium; recovering the pregnant solutions through production wells; and, finally, pumping the uranium bearing solution to the surface for further processing. As compared with conventional mining, in situ leach is recognized as having economic and environmental advantages when properly employed by knowledgeable specialists to extract uranium from suitable sandstone type deposits. Despite its limited applicability to specific types of uranium deposits, in recent years ISL uranium mining has been producing 15 to 21 per cent of world output. In 2002, ISL production was achieved in Australia, China, Kazakhstan, the United States of America and Uzbekistan. Its importance is expected to increase with new projects in Australia, China, Kazakhstan and the Russian Federation. The Technical Meeting on Recent Development in Uranium Resources and Production with Special Emphasis on In Situ Leach Mining, was held in Beijing from 18 to 20 September 2002, followed by the visit of the Yili ISL mine, Xinjiang Autonomous Region, China, from 21 to 23 September 2002. The meeting, held in cooperation with the Bureau of Geology, China National Nuclear Cooperation, was successful in bringing together 59 specialists representing 18 member states and one international organization (OECD/Nuclear Energy Agency). The papers describe a wide variety of activities related to the theme of the meeting. Subjects such as geology, resources evaluation, licensing, and mine restoration were

  5. 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

    discuss their work as well as problems of common interest, particular with respect to the active membership of the mass chain evaluation team responsible for ENSDF. The first two days were dedicated to a combination of organisational, administrative, and technical reviews and discussion papers concerning the progress made and problems that have been encountered during the last two years. The last three days of the meeting, specific mass chain activities, horizontal evaluations and technical issues were discussed. Problems are still being experienced in maintaining a suitable number of mass chain evaluators (expressed as FTE - Full Time Employment). The uncertain future of the Network, partly due to the aging of the majority of existing evaluators and partly due to the fact that evaluators are overburdened with many other research activities and duties, was an important issue at the meeting. This makes it rather difficult to maintain the high quality of evaluations that has been achieved over the years by the meticulous work of Network members, Member States are urged to support the continuing efforts of the Network to train new evaluators by providing the proper working environment in their respective institutions. Thanks to IAEA efforts, six evaluators are currently being supported and are actively contributing to the evaluation effort

  6. Nuclear heat applications: design aspects and operating experience. Proceedings of four technical meetings held between December 1995 and April 1998

    International Nuclear Information System (INIS)

    1998-11-01

    Proven to be safe, reliable, economic and having minimum impact on the environment, nuclear energy is playing an important role in electricity generation producing 175 of the world's electricity. But since most of the world's energy consumption is in the form of heat the market for nuclear heat has already been recognised. Considering the growing experience in application of power reactors for district heating, industrial processes and water desalination IAEA is periodically reviewing progress and new developments of nuclear heat applications. This proceedings includes the papers presented at the following four meetings: Advisory group meeting and consultancy on experience with nuclear heat applications: district heating, process heat and desalination, 13-15 December 1995 and 7-9 february 1996; Advisory group meeting on technology, design and safety aspects of non-electrical application of nuclear energy, 20-24 October 1997; Advisory group meeting on operational modes of nuclear desalination plants, 3-5 November 1997; Advisory group meeting on materials and equipment for the coupling interfaces of nuclear reactors with desalination and district heating plants, 21-23 April 1998. It is structured according to the subject areas: (1) design an safety aspects of nuclear heat application, (2) operational and material aspects of nuclear heat application and (3) operational experience with nuclear heat application. Each paper is described by a separate abstract

  7. Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-08-01

    The Technical Committee Meeting on Fuel Element Modelling at High Burnup and its Experimental Support was recommended by the International Working Group on Fuel Performance and Technology (IWGFPT). Its subject had been touched on in many of the IAEA's activities; however for the first time modellers and experimentalists were brought together to have an exchange of views on the research under way and to identify areas where new knowledge is necessary to improve the safety, reliability and/or economics of nuclear fuel. The timely organization of this meeting in conjunction with the second meeting of the Co-ordinated Research Programme on Fuel Modelling at Extended Burnup, in short ''FUMEX'', allowed fruitful participation of representatives of developing countries which are only rarely exposed to such a scientific event. The thirty-nine papers presented covered the status of codes and experimental facilities and the main phenomena affecting the fuel during irradiation, namely: thermal fuel performance, clad corrosion and pellet-cladding interaction (PCI) and fission gas release (FGR). Refs, figs, tabs

  8. Annual meeting on nuclear technology '92. Technical session 'Nuclear energy discussion'

    International Nuclear Information System (INIS)

    1992-05-01

    The report contains the six special papers red at the 1992 annual conference on nuclear engineering at Karlsruhe, all of which are individually retrievable from the database. They deal with the following subjects: historical development of the basic trends of technology criticism; communication problems in connection with the conveying of technical facts; psycho-sociological patterns of technology anxiety-mental infection or risk consciousness; field of tension between technology and journalism; handling of insecurities; ethical justifiability of nuclear energy use. (HSCH) [de

  9. Control of autonomous ground vehicles: a brief technical review

    Science.gov (United States)

    Babak, Shahian-Jahromi; Hussain, Syed A.; Karakas, Burak; Cetin, Sabri

    2017-07-01

    This paper presents a brief review of the developments achieved in autonomous vehicle systems technology. A concise history of autonomous driver assistance systems is presented, followed by a review of current state of the art sensor technology used in autonomous vehicles. Standard sensor fusion method that has been recently explored is discussed. Finally, advances in embedded software methodologies that define the logic between sensory information and actuation decisions are reviewed.

  10. Meeting

    Indian Academy of Sciences (India)

    At the invitation of the Physical Research. Laboratory, the 58th Annual Meeting of the. Academy was held at Ahmedabad from 6 to 9. November 1992. The meetings were held at the. Physical Research Laboratory (PRL) and the. Space Applications Centre (SAC) and were organized by PRl, in cooperation with ~AC, the.

  11. 78 FR 16860 - Center for Scientific Review; Notice of Closed Meetings

    Science.gov (United States)

    2013-03-19

    ... Committee: Center for Scientific Review Special Emphasis Panel; Neuronal Communication. Date: April 5, 2013... HUMAN SERVICES National Institutes of Health Center for Scientific Review; Notice of Closed Meetings...: Richard D. Crosland, Ph.D., Scientific Review Officer, Center for Scientific Review, National Institutes...

  12. 78 FR 54665 - Center for Scientific Review; Notice of Closed Meetings

    Science.gov (United States)

    2013-09-05

    ... Committee: Center for Scientific Review Special Emphasis Panel; Member Conflicts: Language and Communication... HUMAN SERVICES National Institutes of Health Center for Scientific Review; Notice of Closed Meetings...). Contact Person: Maribeth Champoux, Ph.D., Scientific Review Officer, Center for Scientific Review...

  13. Aquatic Species Program review: proceedings of principal investigators meeting

    Energy Technology Data Exchange (ETDEWEB)

    1985-06-01

    The purpose of the Aquatic Species Program is to improve the productivity, conversion to fuels, and cost efficiency of aquatic plant culture technologies. The emphasis of the program is on developing a mass culture technology for cultivating oil-yielding microalgae in the American southwest. A technical and economic analysis indicated that such a concept would be feasible if (1) lipid yields from microalgae are improved, (2) there is sufficient saline water for large-scale development, and (3) microalgal lipids can be economically converted to conventional fuels. It was determined that fuels from microalgal lipids presented better options than converting the microalgal biomass to either alcohols or methane. All lipids can potentially be catalytically converted to gasoline, or the fatty acids can be converted to substitute diesel fuels. The Southwest has the necessary low, flat, underutilized lands, and carbon dioxide is available from either natural deposits or flue gas from industrial plants. The amount of saline water available will probably determine how much fuel can be produced from aquatic species, and this question should be answered during 1985. The largest constraint of this technology is the economical production of an oil-rich microalgal feedstock. The agenda for the review was divided into four sections: species selection and characterization, applied physiological studies, outdoor mass cultivation, and systems design and analysis. Papers from these presentations are included in these proceedings. Program advances were reported in the areas of species collection and selection, modulated light physiology, mass culture yields, harvesting of microalgae, mass culture facility design and analysis, and assessments on fuel options from microalgae. Separate abstracts have been prepared for each paper for inclusion in the Energy Data Base.

  14. Use and development of coupled computer codes for the analysis of accidents at nuclear power plants. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2007-01-01

    Computer codes are widely used in Member States for the analysis of safety at nuclear power plants (NPPs). Coupling of computer codes, a further tool for safety analysis, is especially beneficial to safety analysis. The significantly increased capacity of new computation technology has made it possible to switch to a newer generation of computer codes, which are capable of representing physical phenomena in detail and include a more precise consideration of multidimensional effects. The coupling of advanced, best estimate computer codes is an efficient method of addressing the multidisciplinary nature of reactor accidents with complex interfaces between disciplines. Coupling of computer codes is very advantageous for studies which relate to licensing of new NPPs, safety upgrading programmes for existing plants, periodic safety reviews, renewal of operating licences, use of safety margins for reactor power uprating, better utilization of nuclear fuel and higher operational flexibility, justification for lifetime extensions, development of new emergency operating procedures, analysis of operational events and development of accident management programmes. In this connection, the OECD/NEA Working Group on the Analysis and Management of Accidents (GAMA) recently highlighted the application of coupled computer codes as an area of 'high collective interest'. Coupled computer codes are being developed in many Member States independently or within small groups composed of several technical organizations. These developments revealed that there are many types and methods of code coupling. In this context, it was believed that an exchange of views and experience while addressing these problems at an international meeting could contribute to the more efficient and reliable use of advanced computer codes in nuclear safety applications. The present publication constitutes the report on the Technical Meeting on Progress in the Development and Use of Coupled Codes for Accident

  15. Strengthening and sustainability of national immunization technical advisory groups (NITAGs) globally: Lessons and recommendations from the founding meeting of the global NITAG network.

    Science.gov (United States)

    Adjagba, Alex; MacDonald, Noni E; Ortega-Pérez, Inmaculada; Duclos, Philippe

    2017-05-25

    National Immunization Technical Advisory Groups (NITAGs) provide independent, evidence-informed advice to assist their governments in immunization policy formation. However, many NITAGs face challenges in fulfilling their roles. Hence the many requests for formation of a network linking NITAGs together so they can learn from each other. To address this request, the Health Policy and Institutional Development (HPID) Center (a WHO Collaborating Center at the Agence de Médecine Préventive - AMP), in collaboration with WHO, organized a meeting in Veyrier-du-Lac, France, on 11 and 12 May 2016, to establish a Global NITAG Network (GNN). The meeting focused on two areas: the requirements for (a) the establishment of a global NITAG collaborative network; and (b) the global assessment/evaluation of the performance of NITAGs. 35 participants from 26 countries reviewed the proposed GNN framework documents and NITAG performance evaluation. Participants recommended that a GNN should be established, agreed on its governance, function, scope and a proposed work plan as well as setting a framework for NITAG evaluation. Copyright © 2017.

  16. Distributed Item Review: Administrator User Guide. Technical Report #1603

    Science.gov (United States)

    Irvin, P. Shawn

    2016-01-01

    The Distributed Item Review (DIR) is a secure and flexible, web-based system designed to present test items to expert reviewers across a broad geographic area for evaluation of important dimensions of quality (e.g., alignment with standards, bias, sensitivity, and student accessibility). The DIR is comprised of essential features that allow system…

  17. Technical Meeting on Establishing Networks for Countries Introducing Nuclear Power. Presentations

    International Nuclear Information System (INIS)

    2013-01-01

    The objectives of the meeting were to: • Learn about existing networking opportunities that may be of interest for embarking countries; • Discuss common challenges among Member States that could be addressed through better networking opportunities; • Determine appropriate sub-networks, such as future owner/operator organizations, heads of nuclear energy programme implementing organizations (NEPIOs), embarking countries and countries with current civil nuclear programmes; and • Discuss effective strategies for creating networks using existing social media platforms

  18. Advanced post-irradiation examination techniques for water reactor fuel. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2002-03-01

    The purpose of the meeting was to provide and overview of the status of post-irradiation examination (PIE) techniques for water cooled reactor fuel assemblies and their components with emphasis given to advanced PIE techniques applied to high burnup fuel. Papers presented at the meeting described progress obtained in non-destructive (e.g. dimensional measurements, oxide layer thickness measurements, gamma scanning and tomography, neutron and X-ray radiography, etc.) and destructive PIE techniques (e.g. microstructural studies, elemental and isotopic analysis, measurement of physical and mechanical properties, etc.) used for investigation of water reactor fuel. Recent practice in high burnup fuel investigation revealed the importance of advanced PIE techniques, such as 3-D tomography, secondary ion mass spectrometry, laser flash, high resolution transmission and scanning electron microscopy, image analysis in microstructural studies, for understanding mechanisms of fuel behaviour under irradiation. Importance and needs for in-pile irradiation of samples and rodlets in instrumented rigs were also discussed. This TECDOC contains 20 individual papers presented at the meeting; each of the papers has been indexed separately

  19. 76 FR 20323 - Hydrographic Services Review Panel Meeting

    Science.gov (United States)

    2011-04-12

    ... most current meeting agenda. Times and agenda topics are subject to change. FOR FURTHER INFORMATION...:// nauticalcharts.noaa.gov/ocslhsro/hsro.htm . SUPPLEMENTARY INFORMATION: The meeting will be open to the public and...) Improve the quality and delivery of navigation products and services; (2) maximize the societal value of...

  20. Proceedings of the technical review on advances in geothermal reservoir technology---Research in progress

    Energy Technology Data Exchange (ETDEWEB)

    Lippmann, M.J. (ed.)

    1988-09-01

    This proceedings contains 20 technical papers and abstracts describing most of the research activities funded by the Department of Energy (DOE's) Geothermal Reservoir Technology Program, which is under the management of Marshall Reed. The meeting was organized in response to several requests made by geothermal industry representatives who wanted to learn more about technical details of the projects supported by the DOE program. Also, this gives them an opportunity to personally discuss research topics with colleagues in the national laboratories and universities.

  1. General meeting. Technical reunion: the numerical and experimental simulation applied to the Reactor Physics

    International Nuclear Information System (INIS)

    2001-10-01

    The SFEN (French Society on Nuclear Energy), organized the 18 october 2001 at Paris, a technical day on the numerical and experimental simulation, applied to the reactor Physics. Nine aspects were discussed, giving a state of the art in the domain:the french nuclear park; the future technology; the controlled thermonuclear fusion; the new organizations and their implications on the research and development programs; Framatome-ANP markets and industrial code packages; reactor core simulation at high temperature; software architecture; SALOME; DESCARTES. (A.L.B.)

  2. 76 FR 8370 - National Toxicology Program (NTP); Office of Liaison, Policy and Review; Meeting of the NTP Board...

    Science.gov (United States)

    2011-02-14

    ... Reproduction Study Design Statistical Methods used in NTP Technical Reports Research Concept: Nanomaterials... meeting, summary minutes will be prepared and made available on the BSC meeting Web site. Attendance and... continuing to adjournment. This meeting is open to the public with attendance limited only by the space...

  3. Abstracts of 4. IAEA technical meeting on the theory of plasma instabilities

    International Nuclear Information System (INIS)

    2009-05-01

    The Fourth IAEA-TM on Theory of Plasma Instabilities provided a forum for open discussion on theoretical and computational physics issues relevant to burning plasma. The meeting covered linear and non-linear theory and simulation of plasma instabilities, including core/edge turbulence, magneto-hydrodynamic (MHD) process, high energy particle driven dynamics and their effects on plasma confinement. Special attention was paid to the multi-scale interaction dynamics in better understanding the burning plasma and also to the modeling of such complex physical processes. The meeting also organized a panel session to discuss the prospect of plasma theory and simulation for future fusion research for the ITER ERA. Young scientists were enthusiastically encouraged to enjoy this session which may stimulate the research for the future. The meeting covered the following topics: (1) Overview: State of the art and importance of multi-scale physics for understanding burning plasmas; (2) Linear and nonlinear instabilities and their theoretical/computational methodologies including critical gradient problem and comparison with experiments; (3) Core/edge turbulent transport including momentum transport, turbulence-profile interaction and barrier formation, etc and their theoretical/ computational understandings; (4) Magneto-hydrodynamic (MHD) instability including energetic particle physics and their impact on confinement in burning plasmas; (5) Physics and modeling of multi-scale interactions and their impact on the plasma performance and control. Those topics were discussed with close relevance to key experimental results. A panel session 'Theoretical Plasma Physics for the ITER ERA' was organized under interdisciplinary aspects with other fields such as astrophysics and fluid dynamics. Each of the abstracts available has been indexed separately

  4. Independent technical review of the Bin and Alcove test programs at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1993-12-01

    This Independent Technical Review (ITR) assessed the need for and technical validity of the proposed Bin and Alcove test programs using TRU-waste at the WIPP site. The ITR Team recommends that the planned Bin and Alcove tests be abandoned, and that new activities be initiated in support of the WIPP regulatory compliance processes. Recommendations in this report offer an alternate path for expeditiously attaining disposal certification and permitting

  5. Developing and Improving Student Non-Technical Skills in IT Education: A Literature Review and Model

    Directory of Open Access Journals (Sweden)

    Marcia Hagen

    2016-06-01

    Full Text Available The purpose of this paper is to identify portions of the literature in the areas of Information Technology (IT management, skills development, and curriculum development that support the design of a holistic conceptual framework for instruction in non-technical skills within the IT higher education context. This article review provides a framework for understanding how the critical success factors related to IT and Information Systems (IS professional success is impacted by developing students’ non-technical skills. The article culminates in a holistic conceptual framework for developing non-technical skills within the IT higher education context. Implications for theory and research are provided.

  6. 75 FR 3542 - Rehabilitation Research and Development Service Scientific Merit Review Board; Notice of Meeting

    Science.gov (United States)

    2010-01-21

    ... DEPARTMENT OF VETERANS AFFAIRS Rehabilitation Research and Development Service Scientific Merit... (Federal Advisory Committee Act) that the Rehabilitation Research and Development Service Scientific Merit... Board is to review rehabilitation research and development applications for scientific and technical...

  7. 75 FR 40036 - Rehabilitation Research and Development Service Scientific Merit Review Board; Notice of Meeting

    Science.gov (United States)

    2010-07-13

    ... DEPARTMENT OF VETERANS AFFAIRS Rehabilitation Research and Development Service Scientific Merit... (Federal Advisory Committee Act) that the Rehabilitation Research and Development Service Scientific Merit... is to review rehabilitation research and development applications for scientific and technical merit...

  8. 77 FR 2096 - Proposal Review Panel for Materials Research; Notice of Meeting

    Science.gov (United States)

    2012-01-13

    ...: Name: Site visit review of the Materials Research Science and Engineering Center (MRSEC) at..., Program Director, Materials Research Science and Engineering Centers Program, Division of Materials..., including technical information; financial data, such as salaries and personal information concerning...

  9. 77 FR 2095 - Proposal Review Panel for Materials Research; Notice of Meeting

    Science.gov (United States)

    2012-01-13

    ...: Name: Site visit review of the Materials Research Science and Engineering Center (MRSEC) at Georgia... Science and Engineering Centers Program, Division of Materials Research, Room 1065, National Science..., including technical information; financial data, such as salaries and personal information concerning...

  10. 75 FR 9001 - Proposal Review Panel for Materials Research; Notice of Meeting

    Science.gov (United States)

    2010-02-26

    ...: Name: Site visit review of the Materials Research Science and Engineering Center (MRSEC) at Colorado.... Contact Person: Dr. Charles Ying, Program Director, Materials Research Science and Engineering Centers... nature, including technical information; financial data, such as salaries and personal information...

  11. 78 FR 5505 - Proposal Review Panel for Materials Research; Notice of Meeting

    Science.gov (United States)

    2013-01-25

    ...: Name: Site Visit review of the Materials Research Science and Engineering Center (MRSEC) at Yale..., Materials Research Science and Engineering Centers Program, Division of Materials Research, Room 1065... technical information; financial data, such as salaries and personal information concerning individuals...

  12. 78 FR 39017 - Proposal Review Panel for Materials Research, Notice of Meeting

    Science.gov (United States)

    2013-06-28

    ...: Name: Site visit review of the Materials Research Science and Engineering Center (MRSEC) at the.... Chuck Bouldin, Program Director, Materials Research Science and Engineering Centers Program, Division of..., including technical information; financial data, such as salaries and personal information concerning...

  13. 77 FR 25503 - Proposal Review Panel for Materials Research; Notice of Meeting

    Science.gov (United States)

    2012-04-30

    ...: Name: Site visit review of the Materials Research Science and Engineering Center (MRSEC) at the... Director, Materials Research Science and Engineering Centers Program, Division of Materials Research, Room... nature, including technical information; financial data, such as salaries and personal information...

  14. 78 FR 30342 - Proposal Review Panel for Materials Research; Notice of Meeting

    Science.gov (United States)

    2013-05-22

    ...: Name: Site visit review of the Materials Research Science and Engineering Center (MRSEC) at Duke.... Jones, Program Director, Materials Research Science and Engineering Centers Program, Division of... confidential nature, including technical information; financial data, such as salaries and personal information...

  15. 77 FR 56236 - Proposal Review Panel for Materials Research; Notice of Meeting

    Science.gov (United States)

    2012-09-12

    ...: Name: Site visit review of the Materials Research Science and Engineering Center (MRSEC) at the... Science and Engineering Centers Program, Division of Materials Research, Room 1065, National Science... technical information; financial data, such as salaries and personal information concerning individuals...

  16. 77 FR 61432 - Proposal Review for Materials Research; Notice of Meeting

    Science.gov (United States)

    2012-10-09

    ...: Name: Site visit review of the Materials Research Science and Engineering Center (MRSEC) at Harvard... Engineering Centers Program, Division of Materials Research, Room 1065, National Science Foundation, 4201... technical information; financial data, such as salaries and personal information concerning individuals...

  17. 78 FR 40519 - Proposal Review Panel for Materials Research; Notice of Meeting

    Science.gov (United States)

    2013-07-05

    ...: Name: Site visit review of the Materials Research Science and Engineering Center (MRSEC) at the.... Charles Ying, Program Director, Materials Research Science and Engineering Centers Program, Division of... a proprietary or confidential nature, including technical information; financial data, such as...

  18. Technical papers presented at a DOE meeting on criteria for cleanup of transuranium elements in soil

    International Nuclear Information System (INIS)

    1984-09-01

    Transuranium element soil contamination cleanup experience gained from nuclear weapons accidents and cleanup at Eniwetok Atoll was reviewed. Presentations have been individually abstracted for inclusion in the data base

  19. Scientific and technical aspects of yogurt fortification: A review

    Directory of Open Access Journals (Sweden)

    Hadi Hashemi Gahruie

    2015-03-01

    Full Text Available Food fortification is one of the most important processes for improvement of the nutrients quality and quantity in food. It can be a very cost effective public health intervention. Due to the high consumption rate of dairy products such as yogurt, fortification of these products will effectively reduce or prevent diseases associated with nutritional deficiencies. The aim of this investigation is to study the technical aspects involved in production of different types of fortified yogurts and their role in disease prevention and correction of deficiencies. In this paper, firstly, fortification is defined and the main reasons behind carrying out this process are presented and then yogurt production process and a variety of minerals, vitamins, and functional ingredients which are used in the process are briefly discussed.

  20. Fuel cycle options for light water reactors and heavy water reactors. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1999-11-01

    In the second half of the 20th century nuclear power has evolved from the research and development environment to an industry that supplies 16% of the world's electricity. By the end of 1997, over 8500 reactor-years of operating experience had been accumulated. Global environmental change, and the continuing increase in global energy supply required to provide increasing populations with an improving standard of living, make the contribution from nuclear energy even more important for the next century. For nuclear power to achieve its full potential and make its needed contribution, it must be safe, economical, reliable and sustainable. All of these factors can be enhanced by judicious choice and development of advanced fuel cycle options. The Technical Committee Meeting (TCM) on Fuel Cycle Options for Light Water Reactors and Heavy Water Reactors was hosted by Atomic Energy of Canada Limited (AECL) on behalf of the Canadian Government and was jointly conducted within the frame of activities of the IAEA International Working Group on Advanced Technologies for Light Water Reactors (IWG-LWR) and the IAEA International Working Group on Advanced Technologies for Heavy Water Reactors (IWG-HWR). The TCM provided the opportunity to have in-depth discussions on important technical topics which were highlighted in the International Symposium on Nuclear Fuel Cycle and Reactor Strategies: Adjusting to New Realities, held in Vienna, 3-6 June 1997. The main results and conclusions of the TCM were presented as input for discussion at the first meeting of the IAEA newly formed International Working Group on Fuel Cycle Options

  1. 78 FR 5558 - Medical Review Board Public Meeting

    Science.gov (United States)

    2013-01-25

    ....m., Eastern Standard Time (E.S.T.). The meeting will be held at the Hilton Alexandria Old Town, 1767 King Street, Alexandria, VA 22314 in Salon BC on the main floor. The Hilton Alexandria Old Town is...

  2. Eighth experts meeting on environmental radioactivity monitoring: Technical and organisational means for an optimised measurement of ambient radioactivity in the environment of nuclear facilities

    International Nuclear Information System (INIS)

    1991-01-01

    The plant-specific emission monitoring and environmental monitoring near nuclear facilities are part of the items of the agreement between the EC and the IAEA, for mutual rapid information in the case of accidents. The lectures presented to the technical discussion meeting deal with the legal and technical aspects involved. Dispersion models, computer-aided dispersion models, computer-aided information systems and advanced programs as well as measuring techniques and results of the emission monitoring and environmental monitoring near nuclear facilities are the aspects of main interest discussed at the meeting. (DG) [de

  3. 76 FR 29746 - Science Advisory Board Staff Office Notification of a Public Meeting of the SAB Mercury Review Panel

    Science.gov (United States)

    2011-05-23

    ... Public Meeting of the SAB Mercury Review Panel AGENCY: Environmental Protection Agency (EPA). ACTION... Office announces a public meeting of the SAB Mercury Review Panel. DATES: The meeting will be held on... FACA and EPA policy, notice is hereby given that the SAB Mercury Review Panel will hold a public...

  4. Models for waste life cycle assessment: Review of technical assumptions

    DEFF Research Database (Denmark)

    Gentil, Emmanuel; Damgaard, Anders; Hauschild, Michael Zwicky

    2010-01-01

    waste LCA models. This review infers that some of the differences in waste LCA models are inherent to the time they were developed. It is expected that models developed later, benefit from past modelling assumptions and knowledge and issues. Models developed in different countries furthermore rely...

  5. Intermediate Technical Review Report : Deliverable D0.4

    DEFF Research Database (Denmark)

    Bygholm, Ann; Buus, Lillian; Svendsen, Brian Møller

    This report provides a coprehensivi overview of the activities of the Mediterranean Virtual Univeristy Project from the contract start for December 2005. It provides a review of the achievements so far and a discussion of issues currently being adressed along with remedial actions. The report als...

  6. Intermediate Technical Review Report : Deliverable D0.4

    DEFF Research Database (Denmark)

    Bygholm, Ann; Buus, Lillian; Svendsen, Brian Møller

    This report provides a coprehensivi overview of the activities of the Mediterranean Virtual Univeristy Project from the contract start for December 2005. It provides a review of the achievements so far and a discussion of issues currently being adressed along with remedial actions. The report also...

  7. Report of the LOFT special review group. Technical report

    International Nuclear Information System (INIS)

    Ross, D.F. Jr.

    1981-02-01

    This report represents the results of the LOFT Special Review Group (LSRG) evaluation of the LOFT program and is submitted to the Commission as an aid in its decision whether to continue NRC support of the LOFT project beyond FY 1982. The principal consensus reached by the LSRG recommends continued NRC support of the LOFT program through FY 1983

  8. RESIDENTIAL WOOD COMBUSTION TECHNOLOGY REVIEW VOLUME 1. TECHNICAL REPORT

    Science.gov (United States)

    This report gives results of a review of the current state-of-the-art of residential wood combustion (RWC). The key environmental parameter of concern was the air emission of particles. The technological status of all major RWC categories -- cordwood stoves, fireplaces, masonry h...

  9. Report of the technical committee meeting 1997 annual workshop on ASSET experience and feedback

    International Nuclear Information System (INIS)

    1997-01-01

    Papers and presentations were made by all participating countries and provided a wide range of perspectives on the use of the ASSET methodology. Generally, the views expressed were positive, however, there were comments on areas were the service could be improved or enhanced. The workshop was divided into three task groups to analyze the self-assessments conducted at Krsko NPP, Slovenia; Dukovany NPP, Czech Republic; and Balakovo NPP, Russian Federation. In addition, they were asked to comment on the recommendations on the ASSET service made by the Consultants' Meeting of 26-30 August 1996 on ''Performance of the IAEA programme on Operational Safety Services''. A presentation was made by Mr. B. Thomas to remind delegates of the ASSET methodologies, and Mr. V. Sivokon demonstrated the latest developments of computer software available for assisting in the plant Self-Assessment process. Refs, figs, tabs

  10. 75 FR 61507 - Center for Scientific Review; Notice of Closed Meetings

    Science.gov (United States)

    2010-10-05

    ... HUMAN SERVICES National Institutes of Health Center for Scientific Review; Notice of Closed Meetings... Committee: Center for Scientific Review Special Emphasis Panel, Analysis of Retinal Diseases. Date: October... Business: Orthopedic and Skeletal Biology. Date: November 8, 2010. Time: 8 a.m. to 6 p.m. Agenda: To review...

  11. 77 FR 13135 - Center for Scientific Review; Notice of Closed Meetings

    Science.gov (United States)

    2012-03-05

    ... HUMAN SERVICES National Institutes of Health Center for Scientific Review; Notice of Closed Meetings... Reproduction. Date: March 23, 2012. Time: 10:30 a.m. to 4:30 p.m. Agenda: To review and evaluate grant... HIV/AIDS Structural Biology. Date: March 27, 2012. Time: 8 a.m. to 5 p.m. Agenda: To review and...

  12. 78 FR 108 - Center for Scientific Review; Notice of Closed Meetings

    Science.gov (United States)

    2013-01-02

    ... HUMAN SERVICES National Institutes of Health Center for Scientific Review; Notice of Closed Meetings... Translational Integrated Review Group Tumor Cell Biology Study Section. Date: January 28-29, 2013. Time: 8:00 a... Review Special Emphasis Panel Member Conflict: Endocrinology, Reproduction and Pregnancy. Date: January...

  13. 78 FR 64513 - Center For Scientific Review; Notice of Closed Meetings

    Science.gov (United States)

    2013-10-29

    ... HUMAN SERVICES National Institutes of Health Center For Scientific Review; Notice of Closed Meetings... Reproduction. Date: November 20, 2013. Time: 10:00 a.m. to 6:00 p.m. Agenda: To review and evaluate grant... Scientific Review Special Emphasis Panel; Program Project: Cell Biology. Date: November 21-22, 2013. Time: 8...

  14. 78 FR 66022 - Center for Scientific Review; Notice of Closed Meetings

    Science.gov (United States)

    2013-11-04

    ... personal privacy. Name of Committee: Center for Scientific Review Special Emphasis Panel, Gastrointestinal..., Bethesda, MD 20895, (Virtual Meeting). Contact Person: Mushtaq A Khan, DVM, Ph.D., Scientific Review..., (Telephone Conference Call). Contact Person: Toby Behar, Ph.D., Scientific Review Officer, Center for...

  15. 77 FR 26790 - Meeting of the Public Safety Officer Medal of Valor Review Board

    Science.gov (United States)

    2012-05-07

    ... Safety Officer Medal of Valor Review Board AGENCY: Office of Justice Programs (OJP), Bureau of Justice... meeting (via conference call-in) of the Public Safety Officer Medal of Valor Review Board (``Board'') to... INFORMATION: The Public Safety Officer Medal of Valor Review Board carries out those advisory functions...

  16. 77 FR 55863 - Proposal Review Panel for Materials Research; Notice of Meeting

    Science.gov (United States)

    2012-09-11

    ...:30 p.m. Place: Princeton University, Princeton, NJ. Type of Meeting: Part open. Contact Person: Dr... Session, Draft and Review Report Reason for Late Notice: Due to scheduling conflicts and the necessity to proceed with the review. Reason for Closing: The work being reviewed may include information of a...

  17. Independent Technical Review of In-Tank Precipitation (ITP) at the Savannah River Site

    International Nuclear Information System (INIS)

    1993-06-01

    An Independent Technical Review of In-Tank Precipitation (ITP) and Extended Sludge Processing (ESP) at the Savannah River Site (SRS) was carried out in March, 1993. The review focused on ITP/ESP equipment and chemical processes, integration of ITP/ESP within the High Level Waste (HLW) and Defense Waste Processing Facility (DWPF) systems, and management and regulatory concerns. Following the ITR executive summary, this report includes: Chapter I--summary assessment; Chapter II--recommendations; and Chapter III--technical evaluations

  18. Independent Technical Review of In-Tank Precipitation (ITP) at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    1993-06-01

    An Independent Technical Review of In-Tank Precipitation (ITP) and Extended Sludge Processing (ESP) at the Savannah River Site (SRS) was carried out in March, 1993. The review focused on ITP/ESP equipment and chemical processes, integration of ITP/ESP within the High Level Waste (HLW) and Defense Waste Processing Facility (DWPF) systems, and management and regulatory concerns. Following the ITR executive summary, this report includes: Chapter I--summary assessment; Chapter II--recommendations; and Chapter III--technical evaluations.

  19. Technical progress review of extraction of uranium from fly ash

    International Nuclear Information System (INIS)

    Gao Renxi; Gao Junning; Wu Qingming; Chen Gang; Wan Hongjin; Zhang Ziyue

    2014-01-01

    The increasing of fly ash in coal-fired power plants at home and abroad year by year and the potential impacts to the environment attracted media attention. Although the extraction of uranium from the fly ash in coal-fired power plants had optional process from technique aspect and sufficient preliminary researches, but considering the low grade of the uranium in fly ash and particularity of the mineral composition, it is easy to have a high cost of extraction. As a consequence, it is not included in the development plan of uranium mining and metallurgy. The present applications of fly ash are only building materials, building roads and pit valley backfill, the resource utilization rate was low and was still in its early stages of development and application. In view of this, the research advances and the latest development trends of extraction of uranium from fly ash at home and abroad were introduced from the technical aspect, and the beneficial analyzes of the prospect and advices to this industry were given. (authors)

  20. 78 FR 31884 - Regulations and Procedures Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-05-28

    ..., filing of petitions and applications and agency #0;statements of organization and functions are examples... implementation of the Export Administration Regulations (EAR) and provides for continuing review to update the EAR as needed. Agenda Public Session 1. Opening remarks by the Chairman. 2. Opening remarks by Bureau...

  1. Non-technical skills of the operating theatre scrub nurse: literature review.

    Science.gov (United States)

    Mitchell, Lucy; Flin, Rhona

    2008-07-01

    This paper is a report of a review to identify the non-technical (cognitive and social) skills used by scrub nurses. Recognition that failures in non-technical skills contributed to accidents in high-risk industries led to the development of research programmes to study the role of cognition and social interactions in operational safety. Recently, psychological research in operating theatres has revealed the importance of non-technical skills in safe and efficient performance. Most of the studies to date have focused on anaesthetists and surgeons. On-line sources and university library catalogues, publications of the Association for Perioperative Practice, National Association of Theatre Nurses and Association of Peri-Operative Registered Nurses were searched in 2007. Studies were included in the review if they presented data from scrub nurses on one or more of their non-technical skills. These findings were examined in relation to an existing medical non-technical skills framework with categories of communication, teamwork, leadership, situation awareness and decision-making. Of 424 publications retrieved, 13 were reviewed in detail. Ten concerned communication and eight of those also had data on teamwork. In 11 papers teamwork was examined, and one focused on nurses' situation awareness, teamwork and communication. None of the papers we reviewed examined leadership or decision-making by scrub nurses. Further work is needed to identify formally the non-technical skills which are important to the role of scrub nurse and then to design training in the identified non-technical skills during the education and development of scrub nurses.

  2. 78 FR 64518 - Center for Scientific Review; Amended Notice of Meeting

    Science.gov (United States)

    2013-10-29

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institutes of Health Center for Scientific Review; Amended Notice of Meeting Notice is hereby given of a change in the meeting of the Social Sciences and Population Studies A Study Section, October 3, 2013, 8:30 a.m. to October 4, 2013, 12:00 p.m., Renaissance...

  3. 75 FR 57298 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2010-09-20

    ... report on progress of research performed under a Cooperative Agreement with the National Science... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics; Notice of Meeting In accordance... announces the following meeting. Name: University of Notre Dame Site Visit in Physics (1208). Date and Time...

  4. 78 FR 25101 - Proposal Review Panel for Physics, Notice of Meeting

    Science.gov (United States)

    2013-04-29

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics, Notice of Meeting In accordance... Physics, 1208 Date and Time: Tuesday, April 30, 2013; 8:00 a.m.-6:00 p.m., Wednesday, May 1, 2013, 8:00 a... Meeting: Partially Closed. Contact Person: Mark Coles, Director of Large Facilities, Division of Physics...

  5. 78 FR 65343 - Center for Scientific Review; Amended Notice of Meeting

    Science.gov (United States)

    2013-10-31

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institutes of Health Center for Scientific Review; Amended Notice of Meeting Notice is hereby given of a change in the meeting of the Somatosensory and Chemosensory Systems Study Section, October 1, 2013, 8:00 a.m. to October 2, 2013, 5:30 p.m., National...

  6. Program and Abstracts: DOE Solar Program Review Meeting 2004, 25--28 October 2004, Denver, Colorado

    Energy Technology Data Exchange (ETDEWEB)

    2004-10-01

    This booklet contains the agenda and abstracts for the 2004 U.S. DOE Solar Energy Technologies Program Review Meeting. The meeting was held in Denver, Colorado, October 25-28, 2004. More than 240 abstracts are contained in this publication. Topic areas for the research papers include laboratory research, program management, policy analysis, and deployment of solar technologies.

  7. 78 FR 66031 - Center for Scientific Review; Amended Notice of Meeting

    Science.gov (United States)

    2013-11-04

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institutes of Health Center for Scientific Review; Amended Notice of Meeting Notice is hereby given of a change in the meeting of the Clinical Neuroplasticity and Neurotransmitters Study Section, October 10, 2013, 08:00 a.m. to October 11, 2013, 05:00 p.m...

  8. 75 FR 27350 - Center for Scientific Review; Amended Notice of Meeting

    Science.gov (United States)

    2010-05-14

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institutes of Health Center for Scientific Review; Amended Notice of Meeting Notice is hereby given of a change in the meeting of the Clinical Molecular... South Main Street, Salt Lake City, UT 84101 which was published in the Federal Register on May 7, 2010...

  9. 75 FR 54156 - Center for Scientific Review; Amended Notice of Meeting

    Science.gov (United States)

    2010-09-03

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institutes of Health Center for Scientific Review; Amended Notice of Meeting Notice is hereby given of a change in the meeting of the Language and Communication Study Section, October 4, 2010, 8 a.m. to October 5, 2010, 5 p.m., Ritz Carlton Hotel, 1150 22nd...

  10. 76 FR 2107 - Human Studies Review Board; Notice of Public Meeting

    Science.gov (United States)

    2011-01-12

    ... ENVIRONMENTAL PROTECTION AGENCY [EPA-HQ-ORD-2011-0970; FRL-9252-3] Human Studies Review Board; Notice of Public Meeting AGENCY: Environmental Protection Agency (EPA). ACTION: Notice. SUMMARY: The U.S. Environmental Protection Agency (EPA or Agency) Office of the Science Advisor (OSA) announces a public meeting...

  11. 75 FR 32461 - Human Studies Review Board; Notice of Public Meeting

    Science.gov (United States)

    2010-06-08

    ... ENVIRONMENTAL PROTECTION AGENCY [EPA-HQ-ORD-2010-0381; FRL-9159-9] Human Studies Review Board; Notice of Public Meeting AGENCY: Environmental Protection Agency (EPA). ACTION: Notice. SUMMARY: The U.S. Environmental Protection Agency's (EPA or Agency) Office of the Science Advisor (OSA) announces a public meeting...

  12. 75 FR 61748 - Human Studies Review Board; Notice of Public Meeting

    Science.gov (United States)

    2010-10-06

    ... ENVIRONMENTAL PROTECTION AGENCY [EPA-HQ-ORD-2010-0797' FRL-9211-1] Human Studies Review Board; Notice of Public Meeting AGENCY: Environmental Protection Agency (EPA). ACTION: Notice. SUMMARY: The U.S. Environmental Protection Agency (EPA or Agency) Office of the Science Advisor (OSA) announces a public meeting...

  13. 76 FR 27652 - Center for Scientific Review; Amended Notice of Meeting

    Science.gov (United States)

    2011-05-12

    ... From the Federal Register Online via the Government Publishing Office ] DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institutes of Health Center for Scientific Review; Amended Notice of Meeting Notice is hereby given of a change in the meeting of the Risk, Prevention and Intervention for Addictions...

  14. 77 FR 45366 - Center for Scientific Review; Notice of Closed Meeting

    Science.gov (United States)

    2012-07-31

    ....S.C. App.), notice is hereby given of the following meeting. The meeting will be closed to the public in accordance with the provisions set forth in sections 552b(c)(4) and 552b(c)(6), Title 5 U.S.C..., Bethesda, MD 20892, (Telephone Conference Call). Contact Person: Yi-Hsin Liu, Ph.D., Scientific Review...

  15. Nuclear Safety: Technical progress review, January--March 1989

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E. G. [ed.

    1989-01-01

    This review journal covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  16. 77 FR 58526 - Pacific Fishery Management Council; Public Meeting; Work Session To Review Proposed Salmon...

    Science.gov (United States)

    2012-09-21

    ... the work session is to discuss and review proposed changes to analytical methods used in salmon... address the emergency. Special Accommodations This meeting is physically accessible to people with...

  17. Conference report. Fourth review meeting of the parties of the Joint Convention

    International Nuclear Information System (INIS)

    Brennecke, Peter

    2012-01-01

    The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, the first legal instrument to directly address these topics on a global scale, was opened for signature 29 September 1997. It entered into force 18 June 2001. The Convention calls for triannual review meetings of the Contracting Parties. Each Contracting Party is required to submit a national report to each review meeting that addresses measures taken to implement each of the obligations of the Convention. The first review meeting took place in 2003. The 4 th review meeting of this Convention took place from 14 to 23 May 2012 at the International Atomic Energy Agency (IAEA) Headquarter in Vienna/Austria. (orig.)

  18. Meeting review: 2002 O'Reilly Bioinformatics Technology Conference.

    Science.gov (United States)

    Counsell, Damian

    2002-01-01

    At the end of January I travelled to the States to speak at and attend the first O'Reilly Bioinformatics Technology Conference. It was a large, well-organized and diverse meeting with an interesting history. Although the meeting was not a typical academic conference, its style will, I am sure, become more typical of meetings in both biological and computational sciences.Speakers at the event included prominent bioinformatics researchers such as Ewan Birney, Terry Gaasterland and Lincoln Stein; authors and leaders in the open source programming community like Damian Conway and Nat Torkington; and representatives from several publishing companies including the Nature Publishing Group, Current Science Group and the President of O'Reilly himself, Tim O'Reilly. There were presentations, tutorials, debates, quizzes and even a 'jam session' for musical bioinformaticists.

  19. UMTRA water sampling technical (peer) review. Responses to observations, comments, and recommendations submitted by C. Warren Ankerberg (Geraghty ampersand Miller, Inc.)

    International Nuclear Information System (INIS)

    1993-08-01

    At the request of the Office of Independent Technical Review for the U.S. Department of Energy (DOE), Uranium Mill Tailings Remedial Action (UMTRA) Project, an independent technical review (peer review) was conducted during the period of September 15-17, 1992. The review was conducted by C. Warren Ankerberg (Geraghty ampersand Miller, Inc., Tampa, Florida) and Don Messinger (Roy F. Weston, Inc., West Chester, Pennsylvania). The peer review included a review of written documentation [water sampling standard operating procedures (SOP)], an inspection of technical reports and other deliverables, a review of staff qualifications and training, and a field visit to evaluate the compliance of field procedures with SOPs. The approach of the peer reviewers was to verify that the program meets the following criteria: Reported results are traceable to and consistent with recorded data. The basic assumptions and acceptance criteria are valid. Data are traceable to their origin and to reported analytical results. The procedures employed are consistent both internally and externally with written SOPs and regulatory guidelines. Inferences and conclusions are soundly based. The procedures and/or reports generated present work that satisfies the local, state and/or Federal regulatory requirements as applicable. The approach is consistent with industry standards and/or state-of-the-art technology, as practical. The data generated by activities are legally defensible and technically sound. UMTRA staff are adequately trained and qualified for the work. This document is a response to the observations, comments, and recommendations submitted by C. Warren Ankerberg following his review. The format of this document is to present the findings and recommendations verbatim from Mr. Ankerberg's report, followed by responses from the UMTRA Project staff. Included in the responses from the UMTRA Project staff are recommended changes in SOPs and strategies for implementing the changes

  20. A review of IAEA's technical co-operation programme

    International Nuclear Information System (INIS)

    Samiei, M.

    2004-01-01

    Full text: The Technical Co-operation (TC) Programme is part of the Agency's mandate 'to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world.' The IAEA's role under this Programme is that of a scientific and technical agency making a discrete but significant contribution to sustainable development goals through the transfer of nuclear science and technology. TC is a high impact programme focusing on development needs with about 800 active projects annually with a budget of over $70M, 30% of which is targeted on training and capacity building in over 100 Member States. Since 1970, over 80,000 scientists and specialists from developing countries have been trained in nuclear science and technology and in nuclear power and safety. A number of trends in the world at large will be likely to influence the Agency's TC programme in the next several years: The use of nuclear technologies in developing countries is growing as local infrastructures improve and technology transfer increases, especially among developing countries; Some countries and institutions are becoming more self-reliant as viable markets develop for nuclear technology, based on an increased awareness of their benefits; As facilities age, safe strategies for life extension and for decommissioning are assuming increasing importance, while there is some renewed positive attention to nuclear power in several parts of the world. Concern is increasing related to the potential for malicious acts involving nuclear facilities or unsecured nuclear and other radioactive material. As the nuclear workforce ages, the management of nuclear knowledge is gaining increasing importance, including the need to maintain the safety and security of nuclear installations and their continued reliable operation. It is difficult to forecast precisely how these trends will influence the assistance requested by Member States, but it is already clear that there will be increased

  1. Meeting

    Indian Academy of Sciences (India)

    The organization and arrangements for the scientific meetings, cultural event and the visits to Lothal and SAC were superb. The Academy is grateful to the Physical Research Laboratory particularly R K Varma, Director, PRL, to the. Institute for Plasma Research and its Director. P K Kaw, to the Space Applications Centre and.

  2. Meeting

    Indian Academy of Sciences (India)

    the Defence Minister, Government of India on some of his experiences in technology development in India. A summary of his lecture appears in this issue. In the afternoon the .... of steel armour for our Light Tank which has found wide application to meet the ... basic issues: how information is encoded in the structure of DNA ...

  3. IAEA Technical Meeting on Innovative Fast Reactor Designs with Enhanced Negative Reactivity Feedback Features. Presentations

    International Nuclear Information System (INIS)

    2012-01-01

    The objective of the TM is to review and discuss the safety characteristics and the performances of the core of innovative fast reactor concepts, as well as to present the ongoing R&D activities in the area of core design and advanced simulation tools and methods for fast reactor core physics analysis. The focus is on fast spectrum cores optimized for actinide utilization and transmutation and, in particular, on core designs with enhanced negative reactivity feedback effects

  4. IAEA Technical Meeting on Innovative Fast Reactor Designs with Enhanced Negative Reactivity Feedback Features. Working Material

    International Nuclear Information System (INIS)

    2012-01-01

    The objective of the TM was to review and discuss the safety characteristics and the performances of the core of innovative fast reactor concepts, as well as to present the ongoing R&D activities in the area of core design and advanced simulation tools and methods for fast reactor core physics analysis. The focus was on fast spectrum cores optimized for actinide utilization and transmutation and, in particular, on core designs with enhanced negative reactivity feedback effects

  5. 75 FR 51082 - Center for Scientific Review; Notice of Closed Meetings

    Science.gov (United States)

    2010-08-18

    ... U.S.C. App.), notice is hereby given of the following meetings. The meetings will be closed to the public in accordance with the provisions set forth in sections 552b(c)(4) and 552b(c)(6), Title 5 U.S.C... Conference Call). Contact Person: Yi-Hsin Liu, PhD, Scientific Review Officer, Center for Scientific Review...

  6. Status review of CHEMVAL2 technical areas, June 1992

    International Nuclear Information System (INIS)

    Bruno, J.; Crawford, M.; Fabriol, R.; Jamet, Ph.; Lang, H.; Read, D.; Tweed, C.; Warwick, P.

    1993-01-01

    The second phase of the CHEMVAL project has the principal aim of advancing the state of validation of predictive geochemical models in defined areas. Target areas are those known to be of concern in radiological assessment, namely temperature effects, ionic strength effects, organic complexation, sorption processes, coprecipitation and solid solution formation, and coupled chemical transport modelling. The first stage of CHEMVAL2 involved production of status reviews, which are now complete and combined in this report. The two remaining stages comprise the execution of the main research programme on code verification and model validation, followed by a more detailed comparison with experimental data, model refinement and final reporting. (author)

  7. Nulcear Safety: Technical progress review, October--December 1988

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1988-01-01

    Nuclear Safety is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  8. Nuclear Safety: Volume 29, No. 3: Technical progress review

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1988-07-01

    Nuclear Safety is a review journal that covers significant development in the field of nuclear safety. Its scope included the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated. Individual papers have been cataloged separately.

  9. Waste management assessment and technical review programme. WATRP. An international peer review service for radioactive waste management activities

    International Nuclear Information System (INIS)

    1994-09-01

    International Atomic Energy Agency provides international peer review services in radioactive waste management to those Member States that have established radioactive waste management programmes. Such services are provided within Waste Management Assessment and Technical Review Programme (WATRP). The main objective of WATRP is to provide international expertise and information on a requested subject in the field of radioactive waste management and to validate that programmes and activities are sound and performing well. Refs, figs and tabs

  10. Technical Meeting on Liquid Metal Reactor Concepts: Core Design and Structural Materials. Working Material

    International Nuclear Information System (INIS)

    2013-01-01

    The objective of the TM on “Liquid metal reactor concept: core design and structural materials” was to present and discuss innovative liquid metal fast reactor (LMFR) core designs with special focus on the choice, development, testing and qualification of advanced reactor core structural materials. Main results arising from national and international R&D programmes and projects in the field were reviewed, and new activities to be carried out under the IAEA aegis were identified on the basis of the analysis of current research and technology gaps

  11. Technical issues related to NUREG 0800, Chapter 18: Human Factors Engineering/Standard Review Plan

    International Nuclear Information System (INIS)

    Savage, J.W.

    1982-01-01

    The revision of Chapter 18 of NUREG 0800, Human Factors Engineering Standard Review Plan (SRP) will be based on SECY 82-111 and guidance contained in NUREG 0700, NUREG 0801 and NUREG 0835, plus other references. In conducting field reviews of control rooms, the NRC has identified technical issues which can be used to enhance the development of the revised version of NUREG 0800, and to establish priorities among the list of possible Branch Technical Positions (BTP) in NUREG 0800, Rev. 0, Table 18.0-2. This report is a compilation of comments and suggestions from the people who used NUREG 0700 in the Control Room field reviews. This information was used to establish possible BTP topic priorities so that the most important BTPs could be issued first. The comments and suggestions are included for HFEB review in conjunction with the table of priorities

  12. 76 FR 6197 - Health Services Research and Development Service Merit Review Board; Notice of Meeting

    Science.gov (United States)

    2011-02-03

    ... management, and nursing research. Applications are reviewed for scientific and technical merit... subcommittee on Nursing Research Initiatives will convene from 8 a.m. to 2 p.m.; the subcommittee for pilot... DEPARTMENT OF VETERANS AFFAIRS Health Services Research and Development Service Merit Review Board...

  13. 75 FR 39734 - Health Services Research and Development Service Merit Review Board; Notice of Meeting

    Science.gov (United States)

    2010-07-12

    ... management, and nursing research. Applications are reviewed for scientific and technical merit... subcommittee on Nursing Research Initiative will convene from 8 a.m. to 2 p.m. and Career Development Award... DEPARTMENT OF VETERANS AFFAIRS Health Services Research and Development Service Merit Review Board...

  14. Robotic Arm-Assisted Sonography: Review of Technical Developments and Potential Clinical Applications.

    Science.gov (United States)

    Swerdlow, Daniel R; Cleary, Kevin; Wilson, Emmanuel; Azizi-Koutenaei, Bamshad; Monfaredi, Reza

    2017-04-01

    Ultrasound imaging requires trained personnel. Advances in robotics and data transmission create the possibility of telesonography. This review introduces clinicians to current technical work in and potential applications of this developing capability. Telesonography offers advantages in hazardous or remote environments. Robotically assisted ultrasound can reduce stress injuries in sonographers and has potential utility during robotic surgery and interventional procedures.

  15. 78 FR 42821 - Agency Information Collection (Technical Industry Standards) Activities Under OMB Review

    Science.gov (United States)

    2013-07-17

    ... Human Resources and Housing Branch, New Executive Office Building, Room 10235, Washington, DC 20503 (202... (Technical Industry Standards) Activities Under OMB Review AGENCY: Office of Acquisition and Logistics... or a Copy of the Submission Contact: Crystal Rennie, Enterprise Records Service (005R1B), Department...

  16. 75 FR 28857 - Agency Information Collection (Technical Industry Standards) Activities Under OMB Review

    Science.gov (United States)

    2010-05-24

    ..., OMB Human Resources and Housing Branch, New Executive Office Building, Room 10235, Washington, DC... (Technical Industry Standards) Activities Under OMB Review AGENCY: Office of Acquisition and Logistics... INFORMATION OR A COPY OF THE SUBMISSION CONTACT: Denise McLamb, Enterprise Records Service (005R1B...

  17. BPA-Solicited Technical Review of "Echo Meadows Project Winter Artificial Recharge: Final Report for 2001 Baseline", Technical Report 2004.

    Energy Technology Data Exchange (ETDEWEB)

    Morgan, David

    2004-02-01

    The purpose of this report was to provide, at BPA's request, a technical review of interim products received for Project 2001-015-00 under contract 6925. BPA sometimes solicits technical reviews for Fish and Wildlife products or issues where outside expertise is required. External review of complex project deliverables assures BPA as a funding agency that the contractor is continuing with scientifically-credible experimental techniques envisioned in the original proposal. If the project's methodology proves feasible, there could be potential applications beyond the project area to similar situations in the Columbia Basin. The Experiment involves artificial flooding during high flow periods and a determination of the portion of the return flows that end up in the Umatilla River during low flow months and within acceptable water quality parameters (e.g., low temperature, few contaminants). Flooding could be a critical water source for aquatic organisms at times of the year when flows in the lower reaches of the Umatilla River are low and water is warmer than would be desired. The experiment was proposed to test whether 'this process, recharges the shallow aquifers of the old flood plain, for natural filtration through the alluvial soils as it returns to the Umatilla River, cleaner and cooler (about 50 degree Fahrenheit) five to six month later (about July and August) substantially cooling the river and [making it] more beneficial to anadromous [fish]'. A substantial amount of preliminary data had been collected and preliminary results were submitted in an interim report 'Echo Meadows Project Winter Artificial Recharge: Final Report for 2001 Baseline (December 2002)'. A substantial amount of addition funding was provided for the last cycle of flooding (Phases II) and final analyses of the full compliment of data collected over the life of the contract (Phase III). Third party scientific review may assist the contractor in producing a

  18. Use of reprocessed uranium. Proceedings of a technical committee meeting held in Vienna, August 2007

    International Nuclear Information System (INIS)

    2009-11-01

    Reprocessed uranium (RepU), the uranium recovered from nuclear processing, is produced by several Member States in their facilities or through commercial contracts. From a sustainable development perspective, recycling of this uranium has become an attractive option for improving the efficiency of natural resource management and reducing radioactive waste accumulation. This publication demonstrates that reprocessing of spent fuel could form a key part of advanced fuel methodologies and describes various reuse options of RepU. In particular, it includes detailed review papers on management, storage, packaging and transport of RepU, reprocessing, utility experience and potential use of RepU. The importance of market aspects, economics and long term perspectives is also addressed

  19. Experimental tests and qualification of analytical methods to address thermohydraulic phenomena in advanced water cooled reactors. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2000-05-01

    Technical Committee Meeting on Experimental Tests and Qualification of Analytical Methods to Address Thermohydraulic Phenomena in Advanced Water Cooled Reactors was convened to review the current status and the remaining needs in this field

  20. PNL technical review of pressurized thermal-shock issues. [PWR

    Energy Technology Data Exchange (ETDEWEB)

    Pedersen, L.T.; Apley, W.J.; Bian, S.H.; Defferding, L.J.; Morgenstern, M.H.; Pelto, P.J.; Simonen, E.P.; Simonen, F.A.; Stevens, D.L.; Taylor, T.T.

    1982-07-01

    Pacific Northwest Laboratory (PNL) was asked to develop and recommend a regulatory position that the Nuclear Regulatory Commission (NRC) should adopt regarding the ability of reactor pressure vessels to withstand the effects of pressurized thermal shock (PTS). Licensees of eight pressurized water reactors provided NRC with estimates of remaining effective full power years before corrective actions would be required to prevent an unsafe operating condition. PNL reviewed these responses and the results of supporting research and concluded that none of the eight reactors would undergo vessel failure from a PTS event before several more years of operation. Operator actions, however, were often required to terminate a PTS event before it deteriorated to the point where failure could occur. Therefore, the near-term (less than one year) recommendation is to upgrade, on a site-specific basis, operational procedures, training, and control room instrumentation. Also, uniform criteria should be developed by NRC for use during future licensee analyses. Finally, it was recommended that NRC upgrade nondestructive inspection techniques used during vessel examinations and become more involved in the evaluation of annealing requirements.