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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. ITER technical advisory committee meeting

    International Nuclear Information System (INIS)

    Fujiwara, M.

    1999-01-01

    The ITER Technical Advisory Committee (TAC) meeting took place on December 20-22, 1999 at the Naka Joint Work Site. The objective of this meeting was to review the document 'Technical Basis for ITER-FEAT Outline Design (ODR)' issued by the Director on December 10. It was also aimed at providing the ITER Meeting scheduled for January 19-20, 2000 in Tokyo with a technical assessment of ODR and recommendations for the optimization of the anticipated plasma performance and engineering design, based on the guidelines approved by the Council in June 1998 and recommendations of the last TAC meeting

  3. ITER technical advisory committee meeting

    International Nuclear Information System (INIS)

    Fujiwara, M.

    2001-01-01

    The 17th Meeting of the ITER Technical Advisory Committee (TAC-17) was held on February 19-22, the ITER Garching Work Site in Germany. The objective of the meeting was to review the Draft Final Design Report of ITER-FEAT and assess the ability of the self-consistent overall design both to satisfy the technical objectives previously defined and to meet the cost limitations. TAC-17 was also organized to confirm that the design and critical elements, with emphasis on the key recommendations made at previous TAC meetings, are such as to extend the confidence in starting ITER construction. It was also intended to provide the ITER Council, scheduled to meet on 27 and 28 February in Toronto, with a technical assessment and key recommendations of the above mentioned report

  4. 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

  5. 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.

  6. ITER technical advisory committee meeting at Garching

    International Nuclear Information System (INIS)

    Fujiwara, M.

    1999-01-01

    The ITER Technical Advisory Committee meeting took place on 24-27 February at the Garching Joint Work Site. According to the discussions at the ITER meeting in Yokohama in October 1998, the Technical Advisory Committee was requested to conduct a thorough review of the document 'Options for the reduced technical objectives / reduced cost ITER'

  7. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

  9. 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

    ... the 2008-9 study on Quantitative Risk Assessment of the State Licensed Radioactive Waste Disposal Area... of vitrified high-level radioactive waste (HLW); determination of waste classification of the melter... NUCLEAR WASTE TECHNICAL REVIEW BOARD Board Meeting: April 27, 2011--Amherst, New York; the U.S...

  10. 75 FR 26743 - Pacific Gas and Electric Company; Notice of Environmental Site Review and Technical Meetings To...

    Science.gov (United States)

    2010-05-12

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 12779-005] Pacific Gas and Electric Company; Notice of Environmental Site Review and Technical Meetings To Discuss Information and Monitoring Needs for a License Application for a Pilot Project May 5, 2010. a. Type of Application: Draft Pilot License Application. b. Project N...

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

    International Nuclear Information System (INIS)

    2003-01-01

    36th Annual Meeting of the Technical Working Group on Fast Reactors, the IAEA Technical Meeting (TM) on 'Review of National Programmes on Fast Reactors and Accelerator Driven Systems (ADS)', hosted by the Korean Atomic Energy Research Institute (KAERI) was attended by TWG-FR Members and Advisers from the following Member States (MS) and International Organizations: Brazil, France, Germany, India, Japan, the Republic of Kazakhstan, the Republic of Korea, the Russian Federation, the United Kingdom, the United States of America, and the OECD/NEA. The objectives of the meeting were to: 1) exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); 2) review the progress since the 35th TWG-FR Annual Meeting, including the status of the actions; 3) consider meeting arrangements for 2003 and 2004; 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 35th TWG-FR Annual Meeting

  12. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    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.

  14. 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...

  15. 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)

  16. 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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    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.

  17. Fifth technical meeting on quality

    International Nuclear Information System (INIS)

    Girard, A.

    1998-01-01

    This article reports on the 5th Technical Meeting on Quality which was held in San Diego on 20-22 October 1997 and which was attended by representatives of the Home and Joint Central Team and of manufacturers currently involved in the Large R and D projects. The meeting made progress towards the finalization of the ITER Quality Manual document for inclusion in the Final Design Report and the definition of the quality necessary for ITER procurement and construction

  18. 75 FR 52737 - Meeting of the Mobile Sources Technical Review Subcommittee

    Science.gov (United States)

    2010-08-27

    .... Jackson, preferably at least 10 days prior to the meeting, to give EPA as much time as possible to process... the Subcommittee's Web Site: http://www.epa.gov/air/caaac/mobile_sources.html . MSTRS listserver subscribers will receive notification when the agenda is available on the Subcommittee web site. To subscribe...

  19. 77 FR 13318 - Meeting of the Mobile Sources Technical Review Subcommittee

    Science.gov (United States)

    2012-03-06

    ... Ms. Krueger or Ms. Jackson, preferably at least 10 days prior to the meeting, to give EPA as much... the Subcommittee's Web site: http://www.epa.gov/air/caaac/mobile_sources.html . MSTRS listserver subscribers will receive notification when the agenda is available on the Subcommittee Web site. To subscribe...

  20. 76 FR 58275 - Meeting of the Mobile Sources Technical Review Subcommittee

    Science.gov (United States)

    2011-09-20

    ..., preferably at least 10 days prior to the meeting, to give EPA as much time as possible to process your... the Subcommittee's Web site: http://www.epa.gov/air/caaac/mobile_sources.html . MSTRS listserver subscribers will receive notification when the agenda is available on the Subcommittee Web site. To subscribe...

  1. 76 FR 19095 - Meeting of the Mobile Sources Technical Review Subcommittee

    Science.gov (United States)

    2011-04-06

    ..., preferably at least 10 days prior to the meeting, to give EPA as much time as possible to process your... Subcommittee's Web site: http://www.epa.gov/air/caaac/mobile_sources.html . MSTRS listserver subscribers will receive notification when the agenda is available on the Subcommittee Web site. To subscribe to the MSTRS...

  2. 77 FR 60430 - Meeting of the Mobile Sources Technical Review Subcommittee

    Science.gov (United States)

    2012-10-03

    ... Ms. Krueger or Ms. Jackson, preferably at least 10 days prior to the meeting, to give EPA as much... Web site: http://www.epa.gov/air/caaac/mobile_sources.html . MSTRS listserver subscribers will receive notification when the agenda is available on the Subcommittee Web site. To subscribe to the MSTRS listserver...

  3. 78 FR 59017 - Meeting of the Mobile Sources Technical Review Subcommittee

    Science.gov (United States)

    2013-09-25

    ... the meeting, to give EPA as much time as possible to process your request. Dated: September 18, 2013... be posted on the Subcommittee's Web site: http://www.epa.gov/air/caaac/mobile_sources.html . MSTRS listserver subscribers will receive notification when the agenda is available on the Subcommittee Web site...

  4. Technical meeting on 'Review of solid and mobile fuels for partitioning and transmutation systems'. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    The topics covered during the Meeting were divided into two Sessions. Session 1 - Qualification of Solid and Mobile Fuels delt with: Neutronic, fuel and material properties of a molten salt transmuter; and Preliminary analysis of transmutation fuels for KALIMER. Session 2 - Reactor Physics and Safety Characteristics of Transmutation Systems based on Solid and Mobile Fuel Types included the following: Activity in NEA for P and T area; IAEA activities in the area of partitioning and transmutation; The R and D activity in Brazil: A conceptual fast energy amplifier ADS cooled by helium double stata Th/U fuel cycle; Closed fuel cycle and contemporary tendencies of the nuclear facilities development; Current Russian activities in P and T area; Pyrochemical reprocessing and nuclear spent fuel disposal project; Fuel selection criteria specific for double stratum minor actinide burners.

  5. IAEA technical committee meeting on pellet injection

    International Nuclear Information System (INIS)

    1993-01-01

    The IAEA Technical Committee Meeting on Pellet Injection, May 10-12, 1993, at the Japan Atomic Energy Research Institute, Naka, Ibaraki-ken, Japan, was held to review the latest results on pellet injection and its effects on plasma confinement. In particular, topics included in the meeting include (i) pellet ablation and particle fueling results, (ii) pellet injection effects on confinement, including improved confinement modes, edge effects, magnetohydrodynamic activity and impurity transport, and (iii) injector technology and diagnostics using pellets. About 30 experts attended and 23 papers were presented. Refs, figs and tabs

  6. ITER technical meeting on nuclear analysis

    International Nuclear Information System (INIS)

    Khripunov, V.

    2000-01-01

    The ITER technical meeting on nuclear analysis was organized on 24-25 February 2000 at the ITER Joint Work Site in Garching. It was clear from the meeting that continuous nuclear analysis is a fundamental part of the design process

  7. 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

  8. 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.

  9. Minutes of the IFMIF technical meetings, May 17-20, 2005, Tokyo, Japan

    International Nuclear Information System (INIS)

    Ida, Mizuho; Nakamura, Hiroo; Yutani, Toshiaki; Maebara, Sunao; Umetsu, Tomotake; Sugimoto, Masayoshi

    2005-08-01

    The International Fusion Materials Irradiation Facility (IFMIF) Technical Meetings were held on May 17-20, 2005 at Japan Atomic Energy Research Institute (JAERI) Tokyo. The main objectives were 1) to review technical status of the subsystems; accelerator, target and test facilities, 2) to technically discuss interface issues between target and test facilities, 3) to review results of peer-reviews performed in the EU and Japan, 4) to harmonize design/experimental activities among the subsystems, 5) to review and discuss the Engineering Validation and Engineering Design Activity (EVEDA) tasks, and 6) to make a report of 1) - 5) to the IFMIF Executive Subcommittee. This report presents a brief summary of the Target Technical, Meeting, Test Facilities Technical Meeting, Target/Test Facilities Interface Meeting, Accelerator Technical Meeting and the Technical Integration Meeting. (author)

  10. 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...

  11. 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

  12. 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

  13. 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...

  14. 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

  15. 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.

  16. 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.

  17. Seventh ITER technical meeting on safety and environment

    International Nuclear Information System (INIS)

    Raeder, J.; Gordon, C.

    2000-01-01

    From February 15 to 18, 2000, the Seventy Technical Meeting on Safety and Environment was held at the Garching Joint Work Site which now hosts the Safety, Environment and Health Group of the ITER Joint Central Team. At this meeting, safety experts from the Home Teams worked with the SEHG members on reviews and agreements on the contents of GSSR and on the tasks and the schedule for the production of GSSR as well as the design information to be used and for the analyses to be done

  18. 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

  19. 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

  20. 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.

  1. 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

  2. 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

  3. 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…

  4. NASA Docking System (NDS) Technical Integration Meeting

    Science.gov (United States)

    Lewis, James L.

    2010-01-01

    This slide presentation reviews the NASA Docking System (NDS) as NASA's implementation of the International Docking System Standard (IDSS). The goals of the NDS, is to build on proven technologies previously demonstrated in flight and to advance the state of the art of docking systems by incorporating Low Impact Docking System (LIDS) technology into the NDS. A Hardware Demonstration was included in the meeting, and there was discussion about software, NDS major system interfaces, integration information, schedule, and future upgrades.

  5. 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)

  6. 49 CFR 552.6 - Technical review.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 6 2010-10-01 2010-10-01 false Technical review. 552.6 Section 552.6... § 552.6 Technical review. The appropriate Associate Administrator conducts a technical review of the petition. The technical review may consist of an analysis of the material submitted, together with...

  7. 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).

  8. 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)

  9. Ninth ITER technical meeting on safety and environment

    International Nuclear Information System (INIS)

    Raeder, J.; Gordon, C.

    2001-01-01

    The ninth ITER Technical Meeting on safety and environment, the last in the course of the ITER Engineering Design Activities (EDA), was held at the ITER Garching Joint Work site, 8 to 10 May 2001. At this Meeting, safety experts from the House Teams worked together with the members of the Safety, Environment and Health Groups (SEHG) of the ITER Joint Central Team (JCT) in the following areas: finalization of the Generic Site Safety report (GSSR) which is considered to be the most important objective of the present work; summary of the safety related R and D work done by the Home Teams for ITER during EDA; review of verification and validation work done on computer codes being applied for Safety and Environment (S and E) analyses; outline of work considered necessary for improving the S and E database, quantifying uncertainties of the code results and preparing the adaptation of ITER to a specific site

  10. 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)

  11. 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)

  12. 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)

  13. 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

  14. 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

  15. 78 FR 33416 - Notification of a Public Meeting of the Science Advisory Board Environmental Justice Technical...

    Science.gov (United States)

    2013-06-04

    ... ENVIRONMENTAL PROTECTION AGENCY [FRL--9819-3] Notification of a Public Meeting of the Science... Agency (EPA). ACTION: Notice. SUMMARY: The EPA Science Advisory Board (SAB) Staff Office announces a public meeting of the SAB Environmental Justice Technical Guidance Review Panel to provide advice through...

  16. 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

  17. 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

  18. Summary of IAEA technical committee meeting on impurity control

    International Nuclear Information System (INIS)

    Itoh, Kimitaka.

    1989-03-01

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

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

    International Nuclear Information System (INIS)

    Humbert, Denis

    2004-03-01

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

  20. 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

  1. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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

  3. 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

  4. 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)

  5. 77 FR 58526 - Pacific Fishery Management Council; Public Meeting; Work Session To Review Proposed Salmon...

    Science.gov (United States)

    2012-09-21

    ... Fishery Management Council; Public Meeting; Work Session To Review Proposed Salmon Methodology Changes...), Commerce. ACTION: Notice of a public meeting. SUMMARY: The Pacific Fishery Management Council's Salmon Technical Team (STT), Scientific and Statistical Committee (SSC) Salmon Subcommittee, and Model Evaluation...

  6. 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...

  7. [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)

  8. 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

  9. 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

  10. Meeting of the Technical Working Group on Fast Reactors (TWG-FR) (39th annual meeting). Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The 39th Annual Meeting of the Technical Working Group on Fast Reactors (TWG FR) was held from 15-19 May 2006 in Beijing, China, at the invitation of the China Institute of Atomic Energy (CIAEA). The meeting was attended by TWG-FR Members and Advisers from the following Member States (MS): Belgium (observer), Brazil, China, France, Germany, India, Italy, Japan, the Republic of Kazakhstan, the Republic of Korea, the Russian Federation, Sweden (observer), the United Kingdom, and the United States. Belarus, Switzerland, the European Commission, and OECD/NEA were unable to participate. Moreover, Prof. Carlo Rubbia, CERN director general emeritus, participated, upon IAEA invitation, in the meeting as distinguished scientist and IAEA expert. Mr. S.C. Chetal, from India (Indira Gandhi Centre for Atomic Research, IGCAR), was appointed chairman. 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 38th TWG-FR Annual Meeting, including the status of the actions; - Consider meeting arrangements for 2006 and 2007; - Reviewed 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 co-ordination 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)

  11. 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.

  12. 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

  13. 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.

  14. 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

  15. 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

  16. 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.

  17. 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

  18. 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

  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. 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.

  1. 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

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

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  3. 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)

  4. Proceedings of the meeting on the technical study at KEK

    Energy Technology Data Exchange (ETDEWEB)

    Honma, H.; Tokumoto, S.; Kosuge, T. [National Lab. for High Energy Physics, Tsukuba, Ibaraki (Japan)] [eds.

    1996-03-01

    This report is a summary report of lectures carried out at the technical meeting on ``control technique of network sequencer application and others`` held by the Technical Information and Library, National Laboratory for High Energy Physics, on November 28th and 29th, 1995. In this meeting, 10 lectures are reported to introduce the control technique in each study field for proposing each common topic subject. They are present status of PS accelerator control, improvement of positron accelerator control system, device controller due to sequencer, data acquisitting (DAQ) system using VMEbus, monitoring and controlling system using sequencer at counter hole, radiation beam line interlock system and network, control of superconducting wiggler through network using Visual Basic, microwave monitoring system for KEKB, data transmission of monitor, and development of machining equipment of mirror for X-ray collecting. (G.K.)

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

    International Nuclear Information System (INIS)

    Humbert, D.; Wickham, A.J.

    2009-05-01

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

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

    International Nuclear Information System (INIS)

    Humbert, D.; Wickham, A.J.

    2006-05-01

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

  7. 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. 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)

  9. 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.)

  10. 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.

  11. 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

  12. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-07-01

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

  15. 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)

  16. 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

  17. 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)

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

    International Nuclear Information System (INIS)

    Clark, R.E.H.

    2004-05-01

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

  19. 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

  20. IAEA Technical Meeting on Innovative Heat Exchanger and Steam Generator Designs for Fast Reactors. Working Material

    International Nuclear Information System (INIS)

    2011-01-01

    The IAEA, within the framework of its Nuclear Energy Department’s Technical Working Group on Fast Reactors (TWG-FR), assists Member States activities in fast reactors technology development areas by providing an umbrella for information exchange [topical Technical Meetings (TMs), Workshops and large Conferences] and collaborative R&D [Coordinated Research Projects (CRPs)]. The Technical meeting on “Innovative Heat Exchanger and Steam Generator Designs for Fast Reactors” was held from 21 – 22 December 2011 in Vienna, addressing Member States’ expressed needs of information exchange in the field of advanced fast reactor design features, with particular attention to innovative heat exchangers and steam generators. The Objective of the TM is to provide a global forum for in-depth information exchange and discussion on the most advanced concepts of heat exchangers and steam generators for fast reactors. More specifically, the objectives are: · Review of the status of advanced fast reactor development activities with special emphasis on design and performance of heat exchangers and steam generators; · Discuss requirements for innovative heat exchangers and steam generators; · Present results of studies and conceptual designs for innovative heat exchangers and steam generators; · Provide recommendations for international collaboration under the IAEA aegis. The meeting agenda of the meeting is in Annex I

  1. Technical meeting on decommissioning of fast reactors after sodium draining. Working material

    International Nuclear Information System (INIS)

    2005-01-01

    The objective of the technical meeting was to provide a forum for in-depth scientific and technical exchange on topics related to the decommissioning experience with fast reactors, in particular with regard to the decommissioning of components after sodium draining. Accordingly, the scope of the meeting covers the review and analyses of the experience gained from the decommissioning of both active sodium loops and sodium cooled fast reactors (e.g., KNK II, Superphenix, RAPSODIE, EBR-II, FERMI, BN-350, BR-10). It is expected that the outcome of the meeting will contribute to the Agency initiative to preserve fast reactor data and knowledge. The main focus of the technical meeting was given on the decommissioning of both active loop and reactor components (e.g., the primary vessel of a sodium-cooled reactor) that have been drained of sodium, but that still conserve some residual amounts of sodium (e.g., films covering the entire surface of the component, or particular sodium heels that cannot be drained)

  2. Assessing Technical Competence in Surgical Trainees: A Systematic Review.

    Science.gov (United States)

    Szasz, Peter; Louridas, Marisa; Harris, Kenneth A; Aggarwal, Rajesh; Grantcharov, Teodor P

    2015-06-01

    To systematically examine the literature describing the methods by which technical competence is assessed in surgical trainees. The last decade has witnessed an evolution away from time-based surgical education. In response, governing bodies worldwide have implemented competency-based education paradigms. The definition of competence, however, remains elusive, and the impact of these education initiatives in terms of assessment methods remains unclear. A systematic review examining the methods by which technical competence is assessed was conducted by searching MEDLINE, EMBASE, PsychINFO, and the Cochrane database of systematic reviews. Abstracts of retrieved studies were reviewed and those meeting inclusion criteria were selected for full review. Data were retrieved in a systematic manner, the validity and reliability of the assessment methods was evaluated, and quality was assessed using the Grading of Recommendations Assessment, Development and Evaluation classification. Of the 6814 studies identified, 85 studies involving 2369 surgical residents were included in this review. The methods used to assess technical competence were categorized into 5 groups; Likert scales (37), benchmarks (31), binary outcomes (11), novel tools (4), and surrogate outcomes (2). Their validity and reliability were mostly previously established. The overall Grading of Recommendations Assessment, Development and Evaluation for randomized controlled trials was high and low for the observational studies. The definition of technical competence continues to be debated within the medical literature. The methods used to evaluate technical competence predominantly include instruments that were originally created to assess technical skill. Very few studies identify standard setting approaches that differentiate competent versus noncompetent performers; subsequently, this has been identified as an area with great research potential.

  3. Approaches to the safety of future nuclear power plants. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1996-09-01

    The Technical Committee Meeting on Approaches to Safety of Future Nuclear Power Plants in Different Countries, held from 29 May to 2 June 1995, contributed to this process. Experts from 14 different countries and two international organizations participated in the meeting, which provided the opportunity to exchange information and to review the answers developed to date to these issues (primarily form the IAEA's technical document ''Development of Safety Principles for the Design of Future Nuclear Power Plants'' IAEA-TECDOC-801) and the report of the International Nuclear Safety Advisory Group ''Basic Safety Principles for Nuclear Power Plants'' (INSAG-3). These references were then used as a starting point for answering the question ''to what degree does general agreement (or harmonization) exist on these desired safety approaches for future reactors, and what opportunities remain for further harmonization? 11 refs, 1 tab

  4. 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

  5. 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.

  6. 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.

  7. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-11-15

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

  9. 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...

  10. 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.

  11. 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

  12. 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)

  13. 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

  14. Utilization of a technical review group during a BWR owners group technical specification improvement study

    International Nuclear Information System (INIS)

    Hansell, H.F.; Moyer, D.P.

    1986-01-01

    A BWR Owners' Group Technical Specification Improvement (TSI) Committee was formed in late 1983. A primary goal of this Committee was to encourage the development of a probabilistic methodology for technical specification improvements which could be readily applied by utilities. The TSI Committee elected to hire a Contractor to develop and demonstrate a method. After the Contractor was selected and has started work, the committee decided to establish a Technical Review Group (TRG) to efficiently and effectively review the Contractor's analyses. The TRG met frequently with the Contractor as the analyses were being performed. These meetings were held at the Contractor's facility in order to allow direct contact between reviewers and individuals performing the work. The TRG was also involved with all major interactions with the NRC. The significance and merit of using a peer review group in this manner is the theme of this paper. In order to present a discussion of the significance and merit of the TRG, the activities are described. The summary of the analytical approach is provided to more full understand the TRG activities

  15. 76 FR 20948 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-04-14

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... of export controls applicable to sensors [[Page 20949

  16. 77 FR 61737 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-10-11

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... level of export controls applicable to sensors and instrumentation equipment and technology. Agenda...

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

    Science.gov (United States)

    2012-06-22

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... of export controls applicable to sensors and instrumentation equipment and technology. Agenda Public...

  18. 75 FR 1339 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-01-11

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... level of export controls applicable to sensors and instrumentation equipment and technology. Agenda...

  19. 77 FR 2270 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-01-17

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... the level of export controls applicable to sensors and instrumentation equipment and technology...

  20. 78 FR 1198 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-01-08

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... level of export controls applicable to sensors and instrumentation equipment and technology. Agenda...

  1. 76 FR 323 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-01-04

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... level of export controls applicable to sensors and instrumentation equipment and technology. Agenda...

  2. 75 FR 39920 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-07-13

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... of export controls applicable to sensors and instrumentation equipment and technology. Agenda Public...

  3. 78 FR 19638 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-04-02

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... level of export controls applicable to sensors and instrumentation equipment and technology. Agenda...

  4. 76 FR 63607 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-10-13

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... level of export controls applicable to sensors and instrumentation equipment and technology. Agenda...

  5. 78 FR 60251 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-10-01

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... level of export controls applicable to sensors and instrumentation equipment and technology. [[Page...

  6. 78 FR 40098 - Sensors And Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-07-03

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors And Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... of export controls applicable to sensors and instrumentation equipment and technology. Agenda Public...

  7. 77 FR 23222 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-04-18

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... of export controls applicable to sensors and instrumentation equipment and technology. Agenda Public...

  8. 75 FR 14426 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-03-25

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... of export controls applicable to sensors and instrumentation equipment and technology. Agenda Public...

  9. 75 FR 62508 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-10-12

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... level of export controls applicable to sensors and instrumentation equipment and technology. Agenda...

  10. 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...

  11. 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...

  12. 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...

  13. 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...

  14. 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...

  15. 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...

  16. 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...

  17. 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...

  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. 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...

  20. 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...

  1. 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

  2. Technical Meeting on Impact of Fukushima Event on Current and Future Fast Reactor Designs. Presentations

    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

  3. 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

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

    International Nuclear Information System (INIS)

    2011-01-01

    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 43rd 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 Project&Budget (P&B) biennium 2012-2013; - Review the IAEA’s ongoing information exchange and 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.)

  5. 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.)

  6. Extracorporeal photopheresis: Review of technical aspects.

    Science.gov (United States)

    Arora, Satyam; Setia, Rasika

    2017-01-01

    Extracorporeal photochemotherapy (ECP) is considered as an immune modulating therapy majorly targeting the T cells of the Immune system. ECP induces an anti-inflammatory condition with tolerogenic responses without inducing a global immunosuppression state which is a typical feature of other therapeutic options such as steroids. Clinical indication of ECP has grown over time since its initial applications. Our review discusses the technical aspects of the concept of photopheresis with the available methods for its clinical applications.

  7. Aircraft digital flight control technical review

    Science.gov (United States)

    Davenport, Otha B.; Leggett, David B.

    1993-01-01

    The Aircraft Digital Flight Control Technical Review was initiated by two pilot induced oscillation (PIO) incidents in the spring and summer of 1992. Maj. Gen. Franklin (PEO) wondered why the Air Force development process for digital flight control systems was not preventing PIO problems. Consequently, a technical review team was formed to examine the development process and determine why PIO problems continued to occur. The team was also to identify the 'best practices' used in the various programs. The charter of the team was to focus on the PIO problem, assess the current development process, and document the 'best practices.' The team reviewed all major USAF aircraft programs with digital flight controls, specifically, the F-15E, F-16C/D, F-22, F-111, C-17, and B-2. The team interviewed contractor, System Program Office (SPO), and Combined Test Force (CTF) personnel on these programs. The team also went to NAS Patuxent River to interview USN personnel about the F/A-18 program. The team also reviewed experimental USAF and NASA systems with digital flight control systems: X-29, X-31, F-15 STOL and Maneuver Technology Demonstrator (SMTD), and the Variable In-Flight Stability Test Aircraft (VISTA). The team also discussed the problem with other experts in the field including Ralph Smith and personnel from Calspan. The major conclusions and recommendations from the review are presented.

  8. 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

  9. 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

  10. 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)

  11. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

  13. 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

  14. Space Solar Power Technical Interchange Meeting 2: SSP TIM 2

    Science.gov (United States)

    Sanders, Jim; Hawk, Clark W.

    1998-01-01

    The 2nd Space Solar Power Technical Interchange Meeting (SSP TIM 2) was conducted September 21st through 24th with the first part consisting of a Plenary session. The summary results of this Plenary session are contained in part one of this report. The attendees were then organized into Working Breakout Sessions and Integrated Product Team (IPT) Sessions for the purpose of conducting in-depth discussions in specific topic areas and developing a consensus as to appropriate study plans and actions to be taken. The Second part covers the Plenary Summary Session, which contains the summary results of the Working Breakout Sessions and IPT Sessions. The appendix contains the list of attendees. The ob'jective was to provide an update for the study teams and develop plans for subsequent study activities. This SSP TIM 2 was initiated and the results reported electronically over the Internet. The International Space Station (ISS) could provide the following opportunities for conducting research and technology (R&T) which are applicable to SSP: (1) Automation and Robotics, (2) Advanced Power Generation, (3) Advanced Power Management & Distribution (PMAD), (4) Communications Systems and Networks, (5) Energy Storage, (6) In Space Propulsion (ISP), (7) Structural Dynamics and Control, and Assembly and (8) Wireless Power Transmission.

  15. Report on the Technical Meeting on Therapeutic Radiopharmaceuticals

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    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

  16. Technical review of externalities issues. Final report

    International Nuclear Information System (INIS)

    Niemeyer, V.

    1994-12-01

    Externalities has become the catchword for a major experiment in electric utility regulation. Together with increased competition as a means for economic regulation, this experiment represents a potential revolution in how electric utilities are regulated. It is very important for utilities and policy makers to understand the technical issues and arguments driving the externality experiment. This Technical Review presents four papers covering topics in economics that may play important roles in this revolution. The four papers are: Economic Issues in the Application of Externalities to Electricity Resource Selection; Climate Change, the Marginal Cost of Carbon Dioxide Emissions and the Implications for Carbon Dioxide Emissions Adders; Positive Externalities and Benefits from Electricity; and Socioeconomic Effects of Externality Adders for Electric Utility Emissions

  17. Fuel failure in water reactors: Causes and mitigation. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2003-03-01

    The objective of this technical meeting (TM) was to review the present knowledge of the causes and mechanisms of fuel failure in water reactors during normal operational conditions. Emphasis has been given to analysis of failure causes and their mitigation by means of design as well as plant and core operation including strategies for operation with failed fuel. Some information on detection techniques (on-line monitoring and diagnostics, flux tilting, sipping techniques, etc) has also been presented. This TM presented also the progress on the above-mentioned subjects since the last meeting held in 1992 (Dimitrovgrad, Russian Federation). The topics covered in the papers were as follows: Experience feedback on fuel reliability (8 papers); Strategies to avoid or mitigate fuel failures (4 papers); Experimental studies on fuel failures and degradation mechanisms (4 papers); Modelling of fuel failure mechanisms (3 papers); Detection and monitoring during operation or outage (4 papers); Modelling and assessment of fuel failures (3 papers)

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

    Science.gov (United States)

    Institute of Education Sciences, 2015

    2015-01-01

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

  19. 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

  20. 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

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

    International Nuclear Information System (INIS)

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

    2009-08-01

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

  2. 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.

  3. 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.

  4. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    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.

  6. 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.)

  7. 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

  8. 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

  9. 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...

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

    Energy Technology Data Exchange (ETDEWEB)

    Schwerer, O [IAEA Nuclear Data Section, Vienna (Austria)

    2006-12-15

    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)

  11. 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)

  12. 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)

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

    International Nuclear Information System (INIS)

    Otsuka, Naohiko

    2011-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Schwerer, O [International Atomic Energy Agency, Nuclear Data Section, Vienna (Austria); Henriksson, H [NEA Data Bank, Issy-les-Moulineaux (France)

    2005-01-15

    This report summarizes the IAEA Technical Meeting on the Network of Nuclear Reaction Data Centres (biennial Data Centre Heads Meeting), held at the Brookhaven National Laboratory, Upton, NY, USA from 4-7 October 2004. The meeting was attended by 20 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, status reports of the participating data centres, and a revised technical protocol for the cooperation of the network. (author)

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

    International Nuclear Information System (INIS)

    Schwerer, O.; Henriksson, H.

    2005-01-01

    This report summarizes the IAEA Technical Meeting on the Network of Nuclear Reaction Data Centres (biennial Data Centre Heads Meeting), held at the Brookhaven National Laboratory, Upton, NY, USA from 4-7 October 2004. The meeting was attended by 20 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, status reports of the participating data centres, and a revised technical protocol for the cooperation of the network. (author)

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

    Science.gov (United States)

    2012-11-02

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting; Rescheduled The Sensors and Instrumentation... that affect the level of export controls applicable to sensors [[Page 66179

  18. 78 FR 63161 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting...

    Science.gov (United States)

    2013-10-23

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting ``Rescheduled'' The Sensors and Instrumentation... that affect the level of export controls applicable to sensors and instrumentation equipment and...

  19. Technical Meeting on Liquid Metal Reactor Concepts: Core Design and Structural Materials. Presentations

    International Nuclear Information System (INIS)

    2013-01-01

    The objective of the Technical Meeting is 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

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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.

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

    International Nuclear Information System (INIS)

    Clark, R.E.H.

    2003-10-01

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

  6. 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

  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. 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.

  9. 78 FR 65265 - Materials Technical Advisory Committee; Notice of Open Meeting

    Science.gov (United States)

    2013-10-31

    .... Report on regime-based activities. 7. SHUTDOWN Feedback. 8. Public Comments and New Business. The open...; Notice of Open Meeting The Materials Technical Advisory Committee will meet on November 14, 2013, 10:00 a... materials and related technology. Agenda Open Session 1. Opening Remarks and Introductions. 2. Remarks from...

  10. IAEA Technical committee meeting on methods used in design of spent fuel storage facilities

    International Nuclear Information System (INIS)

    Vitikainen, E.; Silfverberg, P.

    1985-01-01

    The meeting was held in Espoo, Finland and hosted by the Technical Research Centre of Finland (VTT), and was arranged to report and discuss design methods, licensing practise, operational experience as well as economic aspects connectied with spent fuel storage. This report contains session summaries by the session chairmen and the papers presented at the meeting

  11. 76 FR 16785 - Meeting for Software Developers on the Technical Specifications for Common Formats for Patient...

    Science.gov (United States)

    2011-03-25

    ... designed as an interactive forum where PSOs and software developers can provide input on these technical... contact the Food and Drug Administration (FDA) Office of Equal Employment Opportunity and Disability.... Throughout the meeting there will be interactive discussion to allow meeting participants not only to provide...

  12. 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.)

  13. 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

  14. 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.

  15. Report on the IAEA technical meeting of the International Network of Nuclear Reaction Data Centres

    Energy Technology Data Exchange (ETDEWEB)

    Schwerer, O; Dunaeva, S [International Atomic Energy Agency, Nuclear Data Section, Vienna (Austria); org, S Dunaeva@iaea [eds.

    2007-11-15

    An IAEA Technical Meeting of the International Network of Nuclear Reaction Data Centres was held at IAEA Headquarters, Vienna, Austria, from 8 to 10 October 2007. The meeting was attended by 19 participants from 11 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)

  16. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Schwerer, O [International Atomic Energy Agency, Nuclear Data Section, Vienna (Austria)

    2006-02-15

    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)

  18. 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)

  19. Report on the IAEA technical meeting of the International Network of Nuclear Reaction Data Centres

    International Nuclear Information System (INIS)

    Schwerer, O.; Dunaeva, S.; S.Dunaeva@iaea.org

    2007-11-01

    An IAEA Technical Meeting of the International Network of Nuclear Reaction Data Centres was held at IAEA Headquarters, Vienna, Austria, from 8 to 10 October 2007. The meeting was attended by 19 participants from 11 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)

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

    International Nuclear Information System (INIS)

    Otsuka, Naohiko

    2013-07-01

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

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

    International Nuclear Information System (INIS)

    Chung, Hyun-Kyung

    2013-07-01

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

  2. 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

  3. 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.

  4. Outcome and Perspectives from the First IAEA International Technical Meeting on Statistical Methodologies for Safeguards

    International Nuclear Information System (INIS)

    Norman, C.; Binner, R.; Peter, N. J.; Wuester, J.; Zhao, K.; Krieger, T.; Walczak-Typke, A.C.; Richet, S.; Portaix, C.G.; Martin, K.; Bonner, E.R.

    2015-01-01

    Statistical and probabilistic methodologies have always played a fundamental role in the field of safeguards. In-field inspection approaches are based on sampling algorithms and random verification schemes designed to achieve a designed detection probability for defects of interest (e.g., missing material, indicators of tampering with containment and other equipment, changes of design). In addition, the evaluation of verification data with a view to drawing soundly based safeguards conclusions rests on the application of various advanced statistical methodologies. The considerable progress of information technology in the field of data processing and computational capabilities as well as the evolution of safeguards concepts and the steep increase in the volume of verification data in the last decades call for the review and modernization of safeguards statistical methodologies, not only to improve the efficiency of the analytical processes but also to address new statistical and probabilistic questions. Modern computer-intensive approaches are also needed to fully exploit the large body of verification data collected over the years in the increasing number and diversifying types of nuclear fuel cycle facilities in the world. The first biennial IAEA International Technical Meeting on Statistical Methodologies for Safeguards was held in Vienna from the 16 to 18 October 2013. Recommendations and a working plan were drafted which identify and chart necessary steps to review, harmonize, update and consolidate statistical methodologies for safeguards. Three major problem spaces were identified: Random Verification Schemes, Estimation of Uncertainties and Statistical Evaluation of Safeguards Verification Data for which a detailed list of objectives and actions to be taken were established. Since the meeting, considerable progress was made to meet these objectives. The actions undertaken and their outcome are presented in this paper. (author)

  5. 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

  6. 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...

  7. 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

  8. 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.

  9. Modern Topics in Energy and Power Technical Meeting

    Science.gov (United States)

    2016-09-01

    of the meeting started with 2 talks on plasma and nuclear physics in a session chaired by Mr Morris Berman (ARL). In the first talk, “Energy and...and Nuclear Physics, Chair: Mr. Morris Berman 8:30 Energy and Pulsed Power for National Security Applications: A Naval Perspective Dr. Thomas...merit of the ideas expressed. Tuesday , 14 July, 9:00 Photoelectrochemical Water Splitting, from Fundamentals to Devices John A. Turner

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

    Science.gov (United States)

    2017-05-01

    steadily throughout this event, providing insightful comments, discussion, and active attention . This research was sponsored by the US Army...motivation to have this meeting. Within the RCTA’s contextual domain, a dismounted military setting, most HRI research over the past 5 years has...receive and respond to commands. By addressing these 3 main research gaps, a more thorough understanding of the effects of the UMR’s cueing , motion

  11. 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)

  12. 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.

  13. 76 FR 29333 - Pipeline Safety: Meetings of the Technical Pipeline Safety Standards Committee and the Technical...

    Science.gov (United States)

    2011-05-20

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... Technical Hazardous Liquid Pipeline Safety Standards Committee AGENCY: Pipeline and Hazardous Materials... for natural gas pipelines and for hazardous liquid pipelines. Both committees were established under...

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

  15. 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

  16. Technical meeting on progress in managing, and limiting the consequences of events exceeding the design basis

    International Nuclear Information System (INIS)

    Fabian, H.

    2004-01-01

    The Technical Groups on 'Reactor Safety' and 'Thermodynamics and Fluid Dynamics' of the Kerntechnische Gesellschaft e.V. organized a joint technical meeting on 'Progress in Managing, and Limiting the Consequences of, Events Exceeding the Design Basis' at the FTU Training Center of the Karlsruhe Research Center. The topic chosen, the papers presented, the presenters, and the non-technical part of the program met with lively interest on the part of institutions in the nuclear field. These were the objectives of the technical meeting: - Establishing a forum for communicating relevant topics. - In-depth discussion of the main topic, i.e. the advanced development of reactor safety, research in the field, and its application, in twenty selected papers presented by speakers from different institutions. - Presentation of topical work in a nuclear technology institution, the Karlsruhe Research Center. (orig.) [de

  17. Measurement of residual stress in materials using neutrons. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2005-06-01

    One of the objectives of the IAEA's project on effective utilization of research reactors is to promote the use of the existing research reactors based on their capabilities and is implemented through workshops and technical meetings. Measurement of residual stress is one of the techniques that find wide applications in materials development and testing. The Technical Meeting on Measurement of Residual Stress Using Neutrons was organized to meet this objective. This publication is the outcome of the deliberations during the meeting and the presentations by the participants and is addressed to the research reactor managers, users and designers of facilities for reactor utilization. It will especially benefit those seeking to develop new facilities or upgrade the existing ones to enhance the utilization of their research reactors. Experts with a long experience in developing and using neutron beam instruments in high flux and medium flux research reactors participated in this technical meeting. They presented the design, development and utilization of the facilities at their respective centres and reviewed the current status of the residual stress measurements using neutron beams from research reactors. The sessions included brainstorming on the methodology and data analysis, characterization and standardization of the equipment and identifying the scope for further development. This publication refers to the determination of residual and/or applied stresses in polycrystalline materials using neutron diffraction technique. Stress is developed during the synthesis and use of materials such as alloys and compounds. Measurement of residual stress is essential to improve the quality of synthesized materials and diagnosis of failure and/or reliability of fabricated components. Neutron scattering has played an important role in studying structure and dynamics of condensed matter. Neutron scattering is a non-destructive technique and is useful for testing large samples. The

  18. 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

  19. 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

  20. 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.

  1. 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

  2. Nuclear graphite waste management. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2001-05-01

    The purpose of the seminar was to bring together the specialists dealing with various aspects of radioactive graphite waste management to exchange and review information on the decommissioning, characterisation, processing and disposal of irradiated graphite from reactor cores and other graphite waste associated with reactor operation. The seminar covered radioactive graphite characterisation, the effect of irradiation on graphite components, Wigner energy, radioactive graphite waste treatment, conditioning, interim storage and long term disposal options. Individual papers presented at the seminar were indexed separately

  3. 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)

  4. 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

  5. Technical Review of the Characteristics of Spent Nuclear Fuel Scrap

    International Nuclear Information System (INIS)

    Kuhn, William L.; Abrefah, John; Pitner, Allen L.; Damschen, Dennis W.

    2000-01-01

    Spent Nuclear Fuel scrap generated while washing the SNF in Hanford's K-Basins to prepare it for cold vacuum drying differed significantly from that envisioned during project design. Therefore, a technical review panel evaluated the new information about the physical characteristics of scrap generated during processing by characterizing it based on measured weights and digital photographic images. They examined images of the scrap and from them estimated the volume and hence the masses of inert material and of large fragments of spent fuel. The panel estimated the area of these particles directly from images and by fitting a lognormal distribution to the relative number particles in four size ranges and then obtaining the area-to-volume ratio from the distribution. The estimated area is 0.3 m2 for the mass of scrap that could be loaded into a container for drying, which compares to a value of 4.5 m2 assumed for safe operation of the baseline process. The small quantity of scrap genera ted is encouraging. However, the size and mass of the scrap depend both on processes degrading the fuel while in the basin and on processes catching the scrap during washing, the latter including essentially unintentional filtration as debris accumulates. Therefore, the panel concluded that the estimated surface area meets the criterion for loading scrap into an MCO for drying, but because it did not attempt to evaluate the criterion itself, it is not in a position to actually recommend loading the scrap. Further, this is not a sufficiently strong technical position from which to extrapolate the results from the examined scrap to all future scrap generated by the existing process

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

    International Nuclear Information System (INIS)

    Otuka, Naohiko; Herman, Michal

    2016-07-01

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

  7. 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

  8. 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.

  9. 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

  10. 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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

  11. 78 FR 16849 - Alaska Energy Authority; Notice of Dispute Resolution Panel Meeting and Technical Conference

    Science.gov (United States)

    2013-03-19

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 14241-000] Alaska Energy Authority; Notice of Dispute Resolution Panel Meeting and Technical Conference On March 8, 2013, Commission staff, in response to the filing of a notice of [[Page 16850

  12. Papers presented at the IAEA technical committee meeting on H-mode physics

    International Nuclear Information System (INIS)

    TCV team

    1995-11-01

    The two papers contained in this report deal with ohmic H-modes and effect on confinement of edge localized modes in the TCV tokamak. They were presented by the TCV team at the 1995 IAEA technical committee meeting on H-mode physics. figs., tabs., refs

  13. 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

  14. 76 FR 21043 - Notice of Public Meeting: Technical Aspects of Mandatory Deposit of Published Electronic Works...

    Science.gov (United States)

    2011-04-14

    ... mandatory deposit requirements of the copyright law. The objective is to identify file submission, packaging... mandatory deposit provisions of the copyright law. Under the interim regulation, certain works available... LIBRARY OF CONGRESS Copyright Office [Docket No. 2011-3] Notice of Public Meeting: Technical...

  15. 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

  16. 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

  17. Remote monitoring technical review for light water reactors (Phase 1)

    Energy Technology Data Exchange (ETDEWEB)

    Park, Seung Sik; Yoon, Wan Ki; Na, Won Woo; Kwack, Eun Ho [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-10-01

    The IAEA has been conducting a field trial of a Remote Monitoring System (RMS) at the spent fuel storage, Younggwang 3 nuclear power plant. The system installation plan was initiated after the agreement in the 7th ROK-IAEA safeguards Implementation Review Meeting that was held in Soul, 1998. It describes that IAEA and Korea proceed RM tasks Implementation of RMS at LWRs in the ROK for field trials. The project of RMS is conducting through 3 stages with timing. RMS has been installed for the Phase I of field trial, one of two stages at Younggwang Unit 3 in October 1998. The RMS consists of video systems and a seal at the spent fuel pond area. This report provides a description of the monitoring system and its functions focusing on several technical points of the installation and its 6 month operation at Younggwang Unit 3. Subjects are selected and analyzed in the three chapters, IAEA safeguards policy on Remote Monitoring, the technology, and field test experiences. 8 refs., 12 figs., 12 tabs. (Author)

  18. 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 Federal Advisory Committee Act (Pub. L. 92- 463, as amended), the National Science Foundation announces the following meeting: Name: Proposal Review for the Center for Magnetic Self-Organization in...

  19. 76 FR 79211 - Notice of Public Meeting, North Slope Science Initiative-Science Technical Advisory Panel

    Science.gov (United States)

    2011-12-21

    ... jpayne.blm.gov . Persons who use a telecommunications device for the deaf (TDD) may call the Federal... informed resource management decisions. This meeting will include a review of the development and scenario...

  20. 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

  1. 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)

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

    International Nuclear Information System (INIS)

    Hubert, D.

    2006-01-01

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

  3. 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

  4. 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

  5. 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)

  6. 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

  7. Quality control procedures applied to nuclear instruments. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2008-11-01

    Quality Control (QC), test procedures for Nuclear Instrumentation are important for assurance of proper and safe operation of the instruments, especially with regard to equipment related to radiological safety, human health and national safety. Correct measurements of radiation parameters must be ensured, i.e., accurate measurement of the number of radioactive events, counting times and in some cases accurate measurements of the radiation energy and occurring time of the nuclear events. There are several kinds of testing on nuclear instruments, for example, type-testing done by suppliers, acceptance testing made by the end users, Quality Control tests after repair and Quality Assurance/Quality Controls tests made by end-users. All of these tests are based in many cases on practical guidelines or on the experience of the own specialist, the available standards on this topic also need to be adapted to specific instruments. The IAEA has provided nuclear instruments and supported the operational maintenance efforts of the Member States. Although Nuclear Instrumentation is continuously upgraded, some older or aged instruments are still in use and in good working condition. Some of these instruments may not, however, meet modern requirements for the end-user therefore, Member States, mostly those with emerging economies, modernize/refurbish such instruments to meet the end-user demands. As a result, new instrumentation which is not commercially available, or modernized/refurbished instruments, need to be tested or verified with QC procedures to meet national or international certification requirements. A technical meeting on QC procedures applied to nuclear instruments was organized in Vienna from 23 to 24 August 2007. Existing and required QC test procedures necessary for the verification of operation and measurement of the main characteristics of nuclear instruments was the focus of discussion at this meeting. Presentations made at the technical meeting provided

  8. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-07-01

    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

  10. 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

  11. 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

  12. 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.)

  13. 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.)

  14. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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

  16. 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

  17. 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)

  18. 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.

  19. 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

  20. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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. Refs, figs, tabs.

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

    International Nuclear Information System (INIS)

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

    2003-10-01

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

  3. 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.

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

    International Nuclear Information System (INIS)

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

    2002-09-01

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

  5. 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

  6. 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.

  7. 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)

  8. 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.

  9. 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.

  10. Validation procedures of software applied in nuclear instruments. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2007-09-01

    The IAEA has supported the availability of well functioning nuclear instruments in Member States over more than three decades. Some older or aged instruments are still being used and are still in good working condition. However, those instruments may not meet modern software requirements for the end-user in all cases. Therefore, Member States, mostly those with emerging economies, modernize/refurbish such instruments to meet the end-user demands. New advanced software is not only applied in case of new instrumentation, but often also for new and improved applications of modernized and/or refurbished instruments in many Member States for which in few cases the IAEA also provided support. Modern software applied in nuclear instrumentation plays a key role for their safe operation and execution of commands in a user friendly manner. Correct data handling and transfer has to be ensured. Additional features such as data visualization, interfacing to PC for control and data storage are often included. To finalize the task, where new instrumentation which is not commercially available is used, or aged instruments are modernized/refurbished, the applied software has to be verified and validated. A Technical Meeting on 'Validation Procedures of Software Applied in Nuclear Instruments' was organized in Vienna, 20-23 November 2006, to discuss the verification and validation process of software applied to operation and use of nuclear instruments. The presentations at the technical meeting included valuable information, which has been compiled and summarized in this publication, which should be useful for technical staff in Member States when modernizing/refurbishing nuclear instruments. 22 experts in the field of modernization/refurbishment of nuclear instruments as well as users of applied software presented their latest results. Discussion sessions followed the presentations. This publication is the outcome of deliberations during the meeting

  11. 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

  12. 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)

  13. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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. 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

  16. 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

  17. Steady state operation of tokamaks. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2000-10-01

    The first IAEA Technical Committee Meeting (TCM) on Steady State Operation of Tokamaks was organized to discuss the operations of present long-pulse tokamaks (TRIAM-1M, TORE SUPRA, MT-7, HT-7M, HL-1M) and the plans for future steady-state tokamaks such as SST-1, CIEL, and HT-7U. This meeting, held from 13-15 October 1998, was hosted by the Academia Sinica Institute of Plasma Physics (ASIPP), Hefei, China. Participants from China, France, India, Japan, the Russian Federation, and the IAEA participated in the meeting. There were 18 individual presentations plus general discussions on many topics, including superconducting magnet systems, cryogenics, plasma position control, non-inductive current drive, auxiliary heating, plasma-wall interactions, high heat flux components, particle control, and data acquisition

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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

  19. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    Schwerer, O [International Atomic Energy Agency, Nuclear Data Section, Vienna (Austria)

    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)

  1. 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

  2. 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

  3. 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;

  4. 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

  5. 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

  6. 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

  7. 24 CFR 902.68 - Technical review of results of PHAS Indicators #1 or #4.

    Science.gov (United States)

    2010-04-01

    ... both reviews, a request for technical review must be submitted in writing to the Director of the Real... 24 Housing and Urban Development 4 2010-04-01 2010-04-01 false Technical review of results of PHAS... HOUSING AND URBAN DEVELOPMENT PUBLIC HOUSING ASSESSMENT SYSTEM PHAS Scoring § 902.68 Technical review of...

  8. Committees review activities at December meetings

    Science.gov (United States)

    The Education and Human Resources Committee reported having approved participation in the Association for Women Geoscientist's (AWG) national survey. During the summer of 1983 the AWG designed a 75-question survey targeted to women but also applicable to men. The survey consisted of five sections (in addition to such demographics as age, salary, education, job area, and society membership): feelings and attitude toward job, career/family balance, sexual harassment and discrimination, opinions on national energy and conservation policy, and attitude toward AWG. The questionnaire was mailed to AWG members (just over 1000) and to AGU female members (about 1300). Survey participants were asked to give copies to their male colleagues to create a comparison group. About 25% of the 800 responses were from men. The responses were split about 50/50 between AWG and AGU members. The Education and Human Resources Committee will have the results from the survey presented at their next meeting in Cincinnati, May 15.

  9. A technical basis for meeting waste form stability requirements of 10 CFR 61

    International Nuclear Information System (INIS)

    Chang, W.Y.; Skoski, L.; Eng, R.; Tuite, P.T.

    1988-01-01

    To assure that solidified low level waste forms meet the stability requirements of 10 CFR 61 regulations, the US Nuclear Regulatory Commission (NRC) has published Branch Technical Positions (BTPs) and draft Regulatory Guide on waste form stability. These guidance documents describe the test procedures and acceptance criteria for six stability parameters: leachability, compressive strength, immersion effect, radiation effect, thermal stability and biodegradability. The most recent set of recommended tests and acceptance criteria are presented in the November 1986 Preliminary Draft Regulatory Guide Low Level Waste Form Stability. The objective of this study was to: (1) investigate the regulatory and technical bases for the required stability tests, (2) evaluate the relevance of these tests and acceptance criteria based on actual test results, and (3) recommended alternatives to the testing and acceptance criteria. The latter two objectives are discussed in this paper

  10. 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

  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. 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

  13. 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

  14. 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

  15. IAEA Technical Meeting on Status of IAEA Fast Reactor Knowledge Preservation Initiative. Presentations

    International Nuclear Information System (INIS)

    2013-01-01

    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 available and confidential information on fast neutron systems; • collect data on fast neutron systems provided by participating Member States/International Organizations and encourage participants to contribute in data collection; • provide recommendations for further IAEA initiatives in the field of fast reactor knowledge preservation

  16. 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)

  17. 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.

  18. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    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.

  20. 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

  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. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    Latge, C [ed.; CEA, Direction des Reacteurs Nucleaires, Departement d' Etudes des Reacteurs, CEA-Cadarache, Saint-Paul-lez-Durance (France)

    1997-11-01

    This publication summarizes discussions and presented papers from the Technical Committee meeting on sodium removal and disposal from liquid metal fast reactorsin 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.

  5. 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

  6. Structural behaviour of fuel assemblies for water cooled reactors. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2005-07-01

    At the invitation of the Government of France and in response to a proposal of the IAEA Technical Working Group on Water Reactor Fuel Performance and Technology (TWGFPT), the IAEA convened a Technical Meeting on Fuel Assembly Structural Behaviour in Cadarache, France, from 22 to 26 November 2004. The meeting was hosted by the CEA Cadarache Centre, AREVA Framatome-ANP and Electricite de France. The meeting aimed to provide in depth technical exchanges on PWR and WWER operational experience in the field of fuel assembly mechanical behaviour and the potential impact of future high burnup fuel management on fuel reliability. It addressed in-service experience and remedial solutions, loop testing experience, qualification and damage assessment methods (analytic or experimental ones), mechanical behaviour of the fuel assembly including dynamic and fluid structure interaction aspects, modelling and numerical analysis methods, and impact of the in-service evolution of the structural materials. Sixty-seven participants from 17 countries presented 30 papers in the course of four sessions. The topics covered included the impact of hydraulic loadings on fuel assembly (FA)performance, FA bow and control rod (CR) drop kinetics, vibrations and rod-to-grid wear and fretting, and, finally, evaluation and modelling of accident conditions, mainly from seismic causes. FA bow, CR drop kinetics and hydraulics are of great importance under conditions of higher fuel duties including burnup increase, thermal uprates and longer fuel cycles. Vibrations and rod-to-grid wear and fretting have been identified as a key cause of fuel failure at PWRs during the past several years. The meeting demonstrated that full-scale hydraulic tests and modelling provide sufficient information to develop remedies to increase FA skeleton resistance to hydraulic loads, including seismic ones, vibrations and wear. These proceedings are presented as a book with an attached CD-ROM. The first part of the CD

  7. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Schwerer, O; Wienke, H [eds.

    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. Refs, figs, tabs.

  9. 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

  10. SRTC criticality safety technical review of SRT-CMA-930039

    International Nuclear Information System (INIS)

    Rathbun, R.

    1993-01-01

    Review of SRT-CMA-930039, ''Nuclear Criticality Safety Evaluation (NCSE): DWPF Melter-Batch 1,'' December 1, 1993, has been performed by the Savannah River Technical Center (SRTC) Applied Physics Group. The NCSE is a criticality assessment of the Melt Cell in the DWPF. Additionally, this pertains only to Batch 1 operation, which differs from batches to follow. Plans for subsequent batch operations call for fissile material in the Salt Cell feed-stream, which necessitates a separate criticality evaluation in the future. The NCSE under review concludes that the process is safe from criticality events, even in the event that all lithium and boron neutron poisons are lost, provided uranium enrichments are less than 40%. Furthermore, if all the lithium and as much as 98% of the boron would be lost, uranium enrichments of 100% would be allowable. After a thorough review of the NCSE, this reviewer agrees with that conclusion. This technical review consisted of: an independent check of the methods and models employed, independent calculations application of ANSI/ANS 8.1, verification of WSRC Nuclear Criticality Safety Manual( 2 ) procedures

  11. 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

  12. 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

  13. 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

  14. 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

  15. REQUIREMENT VERIFICATION AND SYSTEMS ENGINEERING TECHNICAL REVIEW (SETR) ON A COMMERCIAL DERIVATIVE AIRCRAFT (CDA) PROGRAM

    Science.gov (United States)

    2017-09-01

    VERIFICATION AND SYSTEMS ENGINEERING TECHNICAL REVIEW (SETR) ON A COMMERCIAL DERIVATIVE AIRCRAFT (CDA) PROGRAM by Theresa L. Thomas September... ENGINEERING TECHNICAL REVIEW (SETR) ON A COMMERCIAL DERIVATIVE AIRCRAFT (CDA) PROGRAM 5. FUNDING NUMBERS 6. AUTHOR(S) Theresa L. Thomas 7...CODE 13. ABSTRACT (maximum 200 words) The Naval Air Systems Command (NAVAIR) systems engineering technical review (SETR) process does not

  16. Technical review of the da Vinci surgical telemanipulator.

    Science.gov (United States)

    Freschi, C; Ferrari, V; Melfi, F; Ferrari, M; Mosca, F; Cuschieri, A

    2013-12-01

    The da Vinci robotic surgical telemanipulator has been utilized in several surgical specialties for varied procedures, and the users' experiences have been widely published. To date, no detailed system technical analyses have been performed. A detailed review was performed of all publications and patents about the technical aspects of the da Vinci robotic system. Published technical literature on the da Vinci system highlight strengths and weaknesses of the robot design. While the system facilitates complex surgical operations and has a low malfunction rate, the lack of haptic (especially tactile) feedback and collisions between the robotic arms remain the major limitations of the system. Accurate, preplanned positioning of access ports is essential. Knowledge of the technical aspects of the da Vinci robot is important for optimal use. We confirmed the excellent system functionality and ease of use for surgeons without an engineering background. Research and development of the surgical robot has been predominant in the literature. Future trends address robot miniaturization and intelligent control design. Copyright © 2012 John Wiley & Sons, Ltd.

  17. Neutron reflectometry: A probe for materials surfaces. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2006-01-01

    Research reactors play an important role in delivering the benefits of nuclear science and technology. The IAEA, through its project on the effective utilization of research reactors, has been providing technical support to Member States and promotes activities related to specific applications. Neutron beam research is one of the main components in materials science studies. Neutron reflectometry is extremely useful for characterizing thin films and layered structures, polymers, oxide coatings on metals and biological membranes. The neutron has been a major probe for investigating magnetic materials. Development of magnetic multilayers is important for diverse applications in sensors, memory devices, etc. The special nature of the interaction of the neutron with matter makes it an important tool to locate low z elements in the presence of high z elements, which is useful in biology and polymer science. The role of neutron reflectometry in research and development in materials science and technology was discussed in a consultants meeting held in 2003. Following this, a technical meeting was organized from 16 to 20 August 2004 in Vienna to discuss the current status of neutron reflectometry, including the instrumentation, data acquisition, data analysis and applications. Experts in the field of neutron reflectometry presented their contributions, after which there was a brainstorming session on various aspects of the technique and its applications. This publication is the outcome of deliberations during the meeting and the presentations by the participants. This publication will be of use to scientists planning to develop a neutron reflectometer at research reactors. It will also help disseminate knowledge and information to material scientists, biologists and chemists working towards characterizing and developing new materials

  18. Independent technical review of Savannah River Site Defense Waste Processing Facility technical issues

    International Nuclear Information System (INIS)

    1992-07-01

    The Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) will vitrify high-level radioactive waste that is presently stored as liquid, salt-cake, and sludge in 51 waste-storage tanks. Construction of the DWPF began in 1984, and the Westinghouse Savannah Company (WSRC) considers the plant to be 100% turned over from construction and 91% complete. Cold-chemical runs are scheduled to begin in November 1992, and hot start up is projected for June 1994. It is estimated that the plant lifetime must exceed 15 years to complete the vitrification of the current, high-level tank waste. In a memo to the Assistant Secretary for Defense Programs (DP-1), the Assistant Secretary for Environmental Restoration and Waste management (EM-1) established the need for an Independent Technical Review (ITR), or the Red Team, to ''review process technology issues preventing start up of the DWPF.'' This report documents the findings of an Independent Technical Review (ITR) conducted by the Department of Energy (DOE), Office of Environmental Restoration and Waste Management (EM), at the request of the Assistant Secretary for Environmental Restoration and Waste Management, of specified aspects of Defense Waste Process Facility (DWPF) process technology. Information for the assessment was drawn from documents provided to the ITR Team by the Westinghouse Savannah River Company (WSRC), and presentations, discussions, interviews, and tours held at the Savannah River Site (SRS) during the weeks of February and March 9, 1992

  19. 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.

  20. 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.

  1. 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...

  2. 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

  3. 75 FR 23223 - Meetings of the Agricultural Policy Advisory Committee for Trade and the Agricultural Technical...

    Science.gov (United States)

    2010-05-03

    ...Notice is hereby given that the Agricultural Policy Advisory Committee for Trade (APAC) and the Agricultural Technical Advisory Committees for Trade (ATACs) will hold closed meetings on May 6, 2010. The advisory committees are administered by the U.S. Department of Agriculture and the Office of the United States Trade Representative (USTR). The meetings are closed to the public in accordance with the Trade Act of 1974, 19 U.S.C. 2155(f)(2), and the Government in the Sunshine Act, 5 U.S.C. 552b(c)(4)(6). USTR has determined that public access to the meetings would seriously compromise the development by the U.S. government of trade policy priorities, negotiating objectives, or bargaining positions with respect to the operation of trade agreements and other matters arising in connection with the development, implementation, and administration of the trade policy of the United States. Topics will include Doha Round negotiations in the World Trade Organization (WTO), WTO accession negotiations, and negotiations in bilateral and regional free trade agreements.

  4. 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)

  5. 78 FR 25309 - Proposal Review Panel Physics; Notice of Meeting

    Science.gov (United States)

    2013-04-30

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel Physics; Notice of Meeting In accordance with..., 2013 8:30 a.m.-6:30 p.m. May 15, 2013 8:30 a.m.-6:00 p.m. Place: University of Maryland, College Park... Physics Frontier Center; National Science Foundation, 4201 Wilson Blvd., Arlington, VA 22230. Telephone...

  6. Proceedings of the fuel cells `95 review meeting

    Energy Technology Data Exchange (ETDEWEB)

    George, T.J.

    1995-08-01

    This document contains papers presented at the Fuel Cells `95` Review Meeting. Topics included solid oxide fuel cells; DOE`s transportation program; ARPA advanced fuel cell development; molten carbonate fuel cells; and papers presented at a poster session. Individual papers have been processed separately for the U.S. DOE databases.

  7. 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

  8. Report From the International Linear Collider Technical Review Committee

    International Nuclear Information System (INIS)

    Loew, Gregory A.

    2003-01-01

    The International Linear Collider Technical Review Committee (ILC-TRC), formed in 1994, was reconvened in February 2001 by the International Committee for Future Accelerators (ICFA) to assess the current technical status of all electron-positron linear collider designs at hand in the world: TESLA, JLC-C, JLC-X/NLC and CLIC. The ILC-TRC worked for exactly two years and submitted its report to ICFA in February 2003. This paper presents the motivation behind the study, the charge to the committee and its organization, a table of machine parameters for 500 GeV c.m. energy and later upgrades to higher energies, the methodology used to assess the designs, and a ranked list of R and D tasks still deemed necessary between now and the time any one of the projects is selected by the HEP community and begins construction. Possible future developments are briefly discussed

  9. 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

  10. 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)

  11. 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

  12. Sustainable Mining Environment: Technical Review of Post-mining Plans

    Directory of Open Access Journals (Sweden)

    Restu Juniah

    2017-12-01

    Full Text Available The mining industry exists because humans need mining commodities to meet their daily needs such as motor vehicles, mobile phones, electronic equipment and others. Mining commodities as mentioned in Government Regulation No. 23 of 2010 on Implementation of Mineral and Coal Mining Business Activities are radioactive minerals, metal minerals, nonmetallic minerals, rocks and coal. Mineral and coal mining is conducted to obtain the mining commodities through production operations. Mining and coal mining companies have an obligation to ensure that the mining environment in particular after the post production operation or post mining continues. The survey research aims to examine technically the post-mining plan in coal mining of PT Samantaka Batubara in Indragiri Hulu Regency of Riau Province towards the sustainability of the mining environment. The results indicate that the post-mining plan of PT Samantaka Batubara has met the technical aspects required in post mining planning for a sustainable mining environment. Postponement of post-mining land of PT Samantaka Batubara for garden and forest zone. The results of this study are expected to be useful and can be used by stakeholders, academics, researchers, practitioners and associations of mining, and the environment.

  13. Technical review of the Sandia Laboratories' Particle Beam Fusion Program

    International Nuclear Information System (INIS)

    1979-01-01

    This report considers the technical aspects of Sandia Laboratories' Particle Beam Fusion Program and examines the program's initial goals, the progress made to date towards reaching those goals, and the future plans or methods of reaching those original or modified goals. A summary of Sandia Laboratories' effort, which seeks to demonstrate that high voltage pulsed power generated high-current electron or light ion beams can be used to ignite a deuterium or tritium pellet, is provided. A brief review and assessment of the Sandia Pulse Power Program is given. Several critical issues and summaries of the committee members' opinions are discussed

  14. 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

  15. 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.

  16. 12th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems

    Energy Technology Data Exchange (ETDEWEB)

    Berk, Herbert L.; Breizman, Boris N.

    2014-02-21

    The 12th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems took place in Austin, Texas (7–11 September 2011). This meeting was organized jointly with the 5th IAEA Technical Meeting on Theory of Plasma Instabilities (5–7 September 2011). The two meetings shared one day (7 September 2011) with presentations relevant to both groups. Some of the work reported at these meetings was then published in a special issue of Nuclear Fusion [Nucl. Fusion 52 (2012)]. Summaries of the Energetic Particle Conference presentations were given by Kazuo Toi and Boris Breizman. They respectively discussed the experimental and theoretical progress presented at the meeting. Highlights of this meeting include the tremendous progress that has been achieved in the development of diagnostics that enables the ‘viewing’ of internal fluctuations and allows comparison with theoretical predictions, as demonstrated, for example, in the talks of P. Lauber and M. Osakabe. The need and development of hardened diagnostics in the severe radiation environment, such as those that will exist in ITER, was discussed in the talks of V. Kiptily and V.A. Kazakhov. In theoretical studies, much of the effort is focused on nonlinear phenomena. For example, detailed comparison of theory and experiment on D-III-D on the n = 0 geodesic mode was reported in separate papers by R. Nazikian and G. Fu. A large number of theoretical papers were presented on wave chirping including a paper by B.N. Breizman, which notes that wave chirping from a single frequency may emanate continuously once marginal stability conditions have been established. Another area of wide interest was the detailed study of alpha orbits in a burning plasma, where losses can come from symmetry breaking due to finite coil number or magnetic field imperfections introduced by diagnostic or test modules. An important area of development, covered by M.A. Hole and D.A. Spong, is concerned with the self

  17. 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

  18. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-12-31

    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 Refs, figs, tabs

  20. 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

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

    International Nuclear Information System (INIS)

    Jang, Misuk; Jeon, Jong Seon; Kang, Hyun Sik; Kim, Seoung Rae

    2016-01-01

    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

  2. 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.

  3. 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

  4. 76 FR 67439 - External Peer Review Meeting for Draft Microbial Risk Assessment Guideline: Pathogenic...

    Science.gov (United States)

    2011-11-01

    ... ENVIRONMENTAL PROTECTION AGENCY [EPA-HQ-ORD-2011-053; FRL-9485-1] External Peer Review Meeting for... review draft does not represent EPA policy. The public may register to attend this peer review meeting as... to consider the comments from the external peer review meeting, along with public comments received...

  5. 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

  6. Results of 6th Review Meeting and Perspective of the 7th Review Meeting of the Convention on Nuclear Safety

    International Nuclear Information System (INIS)

    Lee, Sukho; Kim, Manwoong; You, Jeongwon; Lee, Youngeal

    2017-01-01

    This paper highlighted the objective and role of the Convention on Nuclear Safety organized by the IAEA. The Convention provides Member States to demonstrate and share how to maintain and improve the level of nuclear safety. The results of the 6 th review meeting were implemented for safety improvements and to prepare for 7 th national report. Seven and a half months before the 7 th Review Meeting, the National Report has submitted on steps and measures taken to implement Convention obligations. The Contracting Parties reviewed each other’s reports, and exchanged written questions, written answers and comments. The discussions in the Country Group sessions were generally good with a lively and frank exchange of information. The Country Groups noted the significant measures taken by Contracting Parties to improve nuclear safety and identified a number of good practices to be shared with all Contracting Parties.

  7. 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)

  8. Technical Meeting on Existing and Proposed Experimental Facilities for Fast Neutron Systems. Working Material

    International Nuclear Information System (INIS)

    2013-01-01

    The discussion which followed the different presentations highlighted the following points: • All the Member States representatives participating in the technical meeting welcomed this IAEA initiative and expressed their potential interest in contributing to the catalogue; • Not all the countries with a fast reactor programme were represented at the meeting. In particular, it was noted that there was no participation from China, the Russian Federation and the USA. Even contribution from Sweden and Spain would be beneficial. It will be a task of the IAEA Secretariat to try involving also these countries in the preparation of the catalogue; • The catalogue will focus only on experimental facilities supporting development of liquid metal cooled fast reactors (Sodium, Lead and Lead-Bismuth). For the time being, facilities in support of GFR and MSR research will not be included; • As for countries involved in HLM technology research, only European countries were participating at the meeting, i.e. Belgium, France, Italy and Germany. In order to avoid duplication of the work performed within the European project ADRIANA, representatives from these countries underlined that a condition for their contribution to the IAEA catalogue is the involvement of non-European countries with HLM research programmes; • The advice from the Member States is fundamental to clearly define scope, objectives and content of the catalogue. The plan for its drafting has also to be further discussed with Member States representatives; • The catalogue is also intended to identify gaps and future needs that require further R&D initiatives; • The catalogue will be a useful tool to set up international collaboration

  9. 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

  10. 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

  11. 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

  12. 76 FR 19147 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2011-04-06

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

  13. 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

  14. 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...

  15. 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)

  16. 76 FR 59682 - Erie Boulevard Hydropower L.P.; Notice of Dispute Resolution Panel Meeting and Technical Conference

    Science.gov (United States)

    2011-09-27

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 7518-012] Erie Boulevard Hydropower L.P.; Notice of Dispute Resolution Panel Meeting and Technical Conference On September 16, 2011, Commission staff, in response to the filing of notice of study dispute by the New York State Department of...

  17. Models for waste life cycle assessment: Review of technical assumptions

    DEFF Research Database (Denmark)

    Gentil, Emmanuel; Damgaard, Anders; Hauschild, Michael Zwicky

    2010-01-01

    A number of waste life cycle assessment (LCA) models have been gradually developed since the early 1990s, in a number of countries, usually independently from each other. Large discrepancies in results have been observed among different waste LCA models, although it has also been shown that results...... from different LCA studies can be consistent. This paper is an attempt to identify, review and analyse methodologies and technical assumptions used in various parts of selected waste LCA models. Several criteria were identified, which could have significant impacts on the results......, such as the functional unit, system boundaries, waste composition and energy modelling. The modelling assumptions of waste management processes, ranging from collection, transportation, intermediate facilities, recycling, thermal treatment, biological treatment, and landfilling, are obviously critical when comparing...

  18. 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

  19. 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)

  20. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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 Refs, figs, tabs

  2. 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

  3. 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)

  4. 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

  5. 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

  6. 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)

  7. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    Stephens, J A [ed.

    2001-12-01

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

  9. 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

  10. Space Solar Power Exploratory Research and Technology (SERT) Technical Interchange Meeting 2 (SERT TIM 2)

    Science.gov (United States)

    Howell, Joe; Sanders, Clark W.

    2000-01-01

    The University of Alabama in Huntsville's (UAH) Propulsion Research Center hosted the Space Solar Power Exploratory Research & Technology (SERT) Technical Interchange Meeting TIM) 2 in Huntsville, Alabama December 7-10. 1999 with 126 people in attendance. The SERT program includes both competitively procured activities. which are being implemented through a portfolio of focused R&D investments--with the maximum leveraging of existing resources inside and outside NASA. and guided by these system studies. Axel Roth. Director of the Flight Projects Directorate NASA MSFC, welcomed the SERT TIM 2 participants and challenged them to develop the necessary technologies and demonstrations that will lead to Space Solar Power (SSP) International implementation. Joe Howell, NASA MSFC, reiterated the SERT TIM 2 objectives: 1) Refining and modeling systems approaches for the utilization of SSP concepts and technologies, ranging, from the near-term e.g. for space science, exploration and commercial space applications to the far-term (e. g. SSP for terrestrial markets), including systems concepts, technology, infrastructure (i.g., transportation), and economics. 2) Conducting technology research, development and demonstration activities to produce "proof- of-concept" validation of critical SSP elements for both the nearer and farther-term applications. 3) Initiating partnerships Nationality and Internationally that could be expanded, as appropriate, to pursue later SSP technology and applications (e.g., space science. colonization, etc.). Day one began with the NASA Centers presenting their SERT activities summary since SERT TIM 1 and wound up with a presentation by Masahiro Mori, NASDA titled "NASDA In-house Study for SSP". Demonstration for the Near-Term. Day two began with the SERT Systems Studies and Analysis reports resulting from NRA 8-23 followed by presentations of SERT Technology Demonstrations reports resulting from NRA 8-23. Day two closed with John Mankins presentation

  11. 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

  12. 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

  13. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    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.

  15. 75 FR 70951 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2010-11-19

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics; Notice of Meeting In accordance... announces the following meeting. Name: LIGO Laboratory Annual Review at Hanford Observatory for Physics... Physics, National Science Foundation, (703) 292-7373. Purpose of Meeting: To provide an evaluation of the...

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

    Energy Technology Data Exchange (ETDEWEB)

    Janev, R K

    1999-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-12-01

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

  18. 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)

  19. 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.

  20. 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.

  1. 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

  2. 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

  3. 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

  4. 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...

  5. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

  7. 75 FR 16817 - Meeting for Software Developers on the Technical Specifications for Common Formats for Patient...

    Science.gov (United States)

    2010-04-02

    ... and electronically comparable. This meeting is designed as an interactive forum where PSOs and... contact the Food and Drug Administration (FDA) Office of Equal Employment Opportunity and Disability... specifications. Throughout the meeting there will be interactive discussion to allow meeting participants not...

  8. 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

  9. 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.

  10. 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

  11. 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

  12. 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.

  13. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

  15. 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.

  16. 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

  17. 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

  18. 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

  19. 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

  20. 76 FR 52955 - Medicare Program; Meeting of the Technical Advisory Panel on Medicare Trustee Reports

    Science.gov (United States)

    2011-08-24

    ... Panel's discussion is expected to be very technical in nature and will focus on the actuarial and... discussion is expected to focus on highly technical aspects of estimation involving economics and actuarial science. Panelists are not restricted, however, in the topics that they choose to discuss. Procedure and...

  1. 76 FR 58514 - Medicare Program; Meeting of the Technical Advisory Panel on Medicare Trustee Reports

    Science.gov (United States)

    2011-09-21

    ... to be very technical in nature and will focus on the actuarial and economic assumptions and methods... discussion is expected to focus on highly technical aspects of estimation involving economics and actuarial science. Panelists are not restricted, however, in the topics that they choose to discuss. Procedure and...

  2. 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…

  3. 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

  4. 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...

  5. 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)

  6. 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

  7. 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.

  8. 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...

  9. Proceeding of the 20th technical meeting on nuclear reactor and radiation for KURRI engineers and the 11th technical official group section 5 meeting in Kyoto University

    International Nuclear Information System (INIS)

    2012-04-01

    Five presentations were given with a focus on the measures for the Fukushima Daiichi Nuclear Power Station accident. (1) 'Support activities of KURRI on the measures for the Fukushima nuclear accident': Introduction of the state of personal dispatch and support activities for radiation survey performed at evacuation centers. (2) 'New RI usage-emitting α-ray aiming at single cell': Developing state of a new cell irradiation effect observation system that can perform the localized irradiation of RI-derived He ion while targeting single cell under a microscope. (3) 'Reactivity measurement system at Kyoto University research reactor (KUR)': Explanation of the composition and performance of the system of real time display on the output, reactivity, and cooling water temperature of KUR, etc. and the introduction of that this system used in student experiments. (4) 'Introduction of GPS-linked automatic radiation measuring system, KURAMA': Introduction of a voluntarily developed vehicle-mounted type radiation measurement system that takes into account the local conditions of Fukushima (KURAMA). (5) 'Internal exposure dose evaluation of staff members dispatched to Fukushima': Indication of the methods and results of dose assessment, and report on that exposure management has been properly performed. The 3 of 5 papers presented at the entitled meeting are indexed individually. (A.O.)

  10. 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.

  11. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

  13. 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

  14. 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.

  15. 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

  16. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

  18. 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);…

  19. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-07-01

    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.

  1. Remote technology related to the handling, storage and disposal of spent fuel. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    Reduced radiation exposure, greater reliability and cost savings are all potential benefits of the application of remote technologies to the handling of spent nuclear fuel. Remote equipment and technologies are used to some extent in all facilities handling fuel and high-level wastes whether they are for interim storage, processing/repacking, reprocessing or disposal. In view of the use and benefits of remote technologies, as well as recent technical and economic developments in the area, the IAEA organized the Technical Committee Meeting (TCM) on Remote Technology Related to the Handling, Storage and/or Disposal of Spent Fuel. Twenty-one papers were presented at the TCM, divided into five general areas: 1. Choice of technologies; 2. Use of remote technologies in fuel handling; 3. Use of remote technologies for fuel inspection and characterization; 4. Remote maintenance of facilities; and 5. Current and future developments. Refs, figs and tabs.

  2. 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.

  3. 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.

  4. Radiofrequency launchers for plasma heating and current drive. Report on the IAEA Technical Committee Meeting, held at Naka-machi, Ibaraki-ken, Japan, 10-12 November 1993

    International Nuclear Information System (INIS)

    Kimura, H.; Imai, T.; Yamamoto, T.

    1995-01-01

    The objective of the meeting was to review the present status of the plasma and RF launcher interaction for plasma heating and current drive in various frequency regimes (ion cyclotron to electron cyclotron) and to discuss a possible technical solution for the RF launchers to be installed on large fusion machines. The 23 papers presented during the meeting can be found in the published proceedings. This report of the meeting includes the various contributions presented at the meeting in summary fashion, describing the status of the heating and current drive experiments and the technologies of launching systems with different frequencies, innovative ideas for launching systems for next stage large fusion devices and new RF systems under development. 23 refs, 3 tabs

  5. Team Meetings within Clinical Domains - Exploring the Use of Routines and Technical Support for Communication

    Science.gov (United States)

    Groth, Kristina; Lantz, Ann; Sallnäs, Eva-Lotta; Frykholm, Oscar; Green, Anders

    Today, it is common that a team of clinicians, from different disciplines, instead of one single doctor, care for a patient. This is especially true when it concerns more complicated diseases in highly specialised health care. Going from one doctor to a team of doctors raises new dimensions/problems/issues when deciding about the diagnosis and how to treat the patient. Instead of one person deciding, based on the information given from others, a group of people need to agree on a decision. How do the participants during such decision meetings argue for their experience and skill? What kind of technologies are available and how do they support the communication in the meeting? Måseide (2006), for example, focuses on how different forms of evidence influence and regulate the judgements and decisions of medical practitioners during such meetings. Groth et al. (2008), for example, focuses on the technology used during such meetings, with a focus on audio, video, and images.

  6. 75 FR 45591 - Pipeline Safety: Notice of Technical Pipeline Safety Advisory Committee Meetings

    Science.gov (United States)

    2010-08-03

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Part... Committee Meetings AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA); DOT. ACTION... safety standards, risk assessments, and safety policies for natural gas pipelines and for hazardous...

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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. Refs, figs, tabs.

  9. 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

  10. 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

  11. Meeting challenges through good practice. Using the highlights from the third review meeting of the Convention on Nuclear Safety to improve national regulatory systems

    International Nuclear Information System (INIS)

    Keen, L.J.; Cameron, J.K.

    2006-01-01

    The third review meeting of the Convention on Nuclear Safety (CNS), held in April 2005, demonstrated collective progress on ensuring worldwide nuclear safety. The Contracting Parties highlighted areas of focus to be brought back to the fourth review meeting and also committed to a continuity process to revitalize the review processes under the CNS. Specific progress has been achieved in the first year since the conclusion of the third review meeting, but further commitment to progress is required, by the Contracting Parties and the Secretariat of the IAEA, over the next year, especially if changes to the review processes are to be achieved for the fourth review meeting in 2008. (author)

  12. 78 FR 50144 - Rehabilitation Research and Development Service Scientific Merit Review Board; Notice of Meetings

    Science.gov (United States)

    2013-08-16

    ... Review Board; Notice of Meetings The Department of Veterans Affairs (VA) gives notice under the Federal... Development Service Scientific Merit Review Board will meet from 8 a.m. to 5 p.m. on the dates indicated below: Subcommittee Date(s) Location Career Development Award Program.... August 6, 2013........ VHA National...

  13. 76 FR 66998 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2011-10-28

    ... 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 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...

  15. 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...

  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. 75 FR 15460 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2010-03-29

    ... 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: Proposal Review Panel for Physics, LIGO Site Visit in Louisiana (1208...

  3. 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...

  4. 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...

  5. Meeting embryonic requirements of broilers throughout incubation: a review

    Directory of Open Access Journals (Sweden)

    R Molenaar

    2010-09-01

    Full Text Available During incubation of chicken embryos, environmental conditions, such as temperature, relative humidity, and CO2 concentration, must be controlled to meet embryonic requirements that change during the different phases of embryonic development. In the current review, the effects of embryo temperature, egg weight loss, and CO2 concentration on hatchability, hatchling quality, and subsequent performance are discussed from an embryonic point of view. In addition, new insights related to the incubation process are described. Several studies have shown that a constant eggshell temperature (EST of 37.5 to 38.0°C throughout incubation results in the highest hatchability, hatchling quality, and subsequent performance. Egg weight loss must be between 6.5 and 14.0% of the initial egg weight, to obtain an adequate air cell size before the embryo internally pips. An increased CO2 concentration during the developmental phase of incubation (first 10 days can accelerate embryonic development and hatchability, but the physiological mechanisms of this acceleration are not completely understood. Effects of ar increased CO2 concentration during late incubation also need further investigation. The preincubation warming profile, thermal manipulation, and in ovo feeding are new insights related to the incubation process and show that the optimal situation for the embryo during incubation highly depends on the conditions of the eggs before (storage duration and during incubation (environmental conditions and on the conditions of the chickens after hatching (environmental temperature.

  6. [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.

  7. A Review of Technical Communication Programs Outside the United States.

    Science.gov (United States)

    Alred, Gerald J.

    2001-01-01

    Examines technical communication programs outside the United States and comments on such features as their location in the university structure, links with public relations, the inclusion of internships or practicums, the balance of theory and practice, and typical course offerings. Lists a dozen major programs in seven countries. Concludes that…

  8. 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 d...... 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.......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...

  9. 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

  10. 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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

  11. 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

  12. First generation of fusion power plants: Design and technology. Proceedings of the 2. IAEA technical meeting

    International Nuclear Information System (INIS)

    2008-01-01

    This series of meetings has been initiated under recommendation of the International Fusion Research Council for the IAEA and is expected to initiate, develop and mature ideas on fusion strategy that would be of benefit for all players. The present objectives of this meeting are to provide a forum to discuss concepts, technology and environmental aspects of future fusion power plants, the next step following ITER, their role in future energy mix and to assess a selection of urgent topics aiming at identifying the physics and the technological requirements that ITER and a fusion grade materials developing programme will have to address to support the construction of a DEMO(s) fusion power plant(s) prototype demonstrating viable economics. The meeting was organized in five sessions addressing five topics: - (PPCA) Power Plant Concepts and systems Analysis. - (MCP) Materials analysis/Components design/Plasma requirements - (NE) Non-Electric applications of fusion - (SESE) Social, Economic, Safety and Environmental aspects of fusion - (EP) Energy Policy, strategy and scenario for fusion development. A summary session took place at the end of the meeting. Thirty-three participants representing 12 Countries and 3 International Organizations were present at the meeting

  13. 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)

  14. 76 FR 323 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-01-04

    ... Computing, Technology and Security Issues Thursday, January 27 Closed Session 8. Discussion of matters... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory...), Building 33, Cloud Room, 53560 Hull Street, San Diego, California 92152. The Committee advises the Office...

  15. Minutes of Technical Division Steering Committee Meeting July 14, 1953, Savannah River Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Evans, L.C.

    1953-07-24

    Agreements reached on security include classification and security regulations. Safety agreements include a problem with excessive heat in the metallurgy section. Other topics discussed include Building 777, CMX, hydrisides, and separations. Appendices include information on financial status and the status of technical division studies.

  16. 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.

  17. 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)

  18. 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.

  19. Systems for deep brain stimulation: review of technical features.

    Science.gov (United States)

    Amon, A; Alesch, F

    2017-09-01

    The use of deep brain stimulation (DBS) is an important treatment option for movement disorders and other medical conditions. Today, three major manufacturers provide implantable systems for DBS. Although the underlying principle is basically the same for all available systems, the differences in the technical features vary considerably. This article outlines aspects regarding the technical features of DBS systems. The differences between voltage and current sources are addressed and their effect on stimulation is shown. To maintain clinical benefit and minimize side effects the stimulation field has to be adapted to the requirements of the patient. Shaping of the stimulation field can be achieved by the electrode design and polarity configuration. Furthermore, the electric signal consisting of stimulation rate, stimulation amplitude and pulse width affect the stimulation field. Interleaving stimulation is an additional concept, which permits improved treatment outcomes. Therefore, the electrode design, the polarity, the electric signal, and the concept of interleaving stimulation are presented. The investigated systems can be also categorized as rechargeable and non-rechargeable, which is briefly discussed. Options for interconnecting different system components from various manufacturers are presented. The present paper summarizes the technical features and their combination possibilities, which can have a major impact on the therapeutic effect.

  20. 44th Plenary Meeting Report of the Scientific, Technical and Economic Committee for Fisheries (PLEN-13-03)

    DEFF Research Database (Denmark)

    Casey, J.; Abella, J. A.; Andersen, J.

    The Scientific, Technical and Economic Committee for Fisheries hold its 44th plenary on 4-8 November 2013 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 the economic performance of the EU aquaculture and fish processing sectors, fishing effort regime evaluations, and review of stock advice....

  1. 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.

  2. 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.

  3. 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...

  4. 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... business Thursday, November 7, 2013, to RSVP to receive specific instructions on how to participate. Dated...

  5. 78 FR 58534 - Warm Springs Irrigation District; Notice of Technical Meeting

    Science.gov (United States)

    2013-09-24

    ... confertiflora requested by the U.S. Bureau of Land Management on June 7, 2013; the coordination of the National... Agenda: 1. Introduction. 2. Meeting objectives. 3. Plant survey discussion. 4. NEPA coordination. 5... phone. Please contact Kelly Wolcott at [email protected] or (202) 502-6480 by close of business...

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-01-01

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

  7. 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

  8. [Perfusion imaging: Instrumentation, modeling, and radiopharmaceuticals: Report of the scientific meeting: Final technical report

    International Nuclear Information System (INIS)

    Graham, M.M.

    1987-01-01

    This meeting provided an excellent overview of the state-of-the-art in perfusion imaging from the viewpoints of mathematical data analysis, radiochemical synthesis and evaluation, and instrumentation physics. The participants and audience had an opportunity to see how each of these aspects is essential for continued progress in this field

  9. Design meeting on reduced technical objectives/reduced cost ITER options

    International Nuclear Information System (INIS)

    Spears, W.

    1999-01-01

    At this meeting, which took place at Garching, Germany in January 1999, means of reducing the overall cost for ITER to 50% where discussed. It was felt that a smaller plasma of high elongation and high triangularity was a step in the right direction. Further steps would include cheaper magnetic field coils, cheaper in-vessel components and also costly buildings

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

    International Nuclear Information System (INIS)

    1977-01-01

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

  11. Internet and Audiology: A Review of the Second International Meeting.

    Science.gov (United States)

    Laplante-Lévesque, Ariane; Lunner, Thomas; Andersson, Gerhard; Preminger, Jill E

    2016-10-01

    This article describes the Second International Meeting on Internet and Audiology, which took place at the Eriksholm Research Centre, Oticon A/S, Denmark September 24 to 25, 2015, and introduces the research forum arising from the meeting. The potential gains of the Internet within audiology are framed within the central role of quality connections among people, ideas, and objects. First, the meeting is summarized. Second, the 11 articles arising from the meeting and collected in this research forum are grouped into 2 themes: design and evaluation. Last, the benefits of interoperability and standardization are discussed. We look forward to the day when the Internet is an integral part of audiology, and we invite readers to attend future editions of the International Meeting on Internet and Audiology.

  12. Proceedings of a NEA/CSNI-UNIPEDE specialist meeting on improving technical specifications for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1987-07-01

    This CSNI specialist meeting on improving technical specifications for nuclear power plants is sponsored by the OECD Nuclear Energy Agency jointly with UNIPEDE. Technical specifications for nuclear power plants are in a way a prescription which has a direct bearing on the success or failure of the particular installation, and on the success or failure of fission energy around the world. It is therefore highly important that these prescriptions are made as clear and as concise as possible and that it distinguishes requirements which are essential for public health and safety, from the many others which are less important accordingly. The conference was held in september 1987 in madrid (Spain); it is composed of about 40 papers grouped into 8 sessions: invited papers (6 papers), international survey results (1 paper), limiting conditions for operation (8 papers), maintenance and testing (4 papers), actions statements and allowed outage times (8 papers), methodology and technical justification (8 papers), future trends and alternative approaches (4 papers), and a final panel

  13. 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

  14. 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

  15. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-08-15

    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.

  17. Minutes of Technical Division Steering Committee meeting January 11, 1955, Savannah River Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Evans, L.C.

    1955-01-18

    The following studies were approved: 8501 - non-destructive testing, 8502 - 300 Area process development, 8503 - new fuel element fabrication, 8504 - protective coatings for new fuel elements, 8505 - corrosion, 8508 - instrument development in 300 Area, 8514 - instrument development in 100 Area, 8515 - instrument development in 200 Area, and 8524 - new LM elements. Information and Safety agreements are listed, and information in appended on the following topics: financial status, instrument development program, metallurgical development program, and Technical Division study status.

  18. 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

  19. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

  1. 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

  2. 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

  3. 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.

  4. 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

  5. Summary Report of the Technical Meeting on Primary Radiation Damage: From Nuclear Reaction to Point Defects

    International Nuclear Information System (INIS)

    Stoller, R. E.; Nordlund, K.; Simakov, S.P.

    2012-11-01

    The Meeting was convened to bring together the experts from both the nuclear data and materials research communities because of their common objective of accurately characterizing irradiation environments and resulting material damage. The meeting demonstrated that significant uncertainties remain regarding both the status of nuclear data and the use of these data by the materials modeling community to determine the primary damage state obtained in irradiated materials. At the conclusion of the meeting, the participants agreed that there is clear motivation to initiate a CRP that engages participants from the nuclear data and materials research communities. The overall objective of this CRP would be to determine the best possible parameter (or a few parameters) for correlating damage from irradiation facilities with very different particle types and energy spectra, including fission and fusion reactors, charged particle accelerators, and spallation irradiation facilities. Regarding progress achieved during the last decade in the atomistic simulation of primary defects in crystalline materials, one of the essential and quantitative outcomes from the CRP is expected to be cross sections for point defects left after recoil cascade quenching. (author)

  6. Technical Meeting on Design, Manufacturing and Irradiation Behaviour of Fast Reactors Fuels. Presentations

    International Nuclear Information System (INIS)

    2011-01-01

    The purpose of this meeting was to enable a rationalization and advancement of the design and manufacturing processes, a better selection of promising fuels, and a reduction of the time and costs currently required for R and D and testing, as well as to contribute to the improvement of the safety features of fuels under all operational states and accidental conditions. An overview of the status and perspective of the design, manufacturing and irradiation behaviour of fast reactors fuels were provided during this meeting. The main objectives are the following: Ensure sharing and dissemination of knowledge and expertise; Discuss specific features and issues of existing fuels; Improve knowledge and data for the design and engineering of fast reactor fuel and core structural materials; Discuss perspectives on advanced fuels; Consider modern technological, design and testing tools enabling reliable performance of fuels in current and planned operational environments; Establish international consensus in the developmental efforts on advanced fast reactor technologies, including collaborative programs and experiments. Contribute to the preparation and outline of the planned IAEA Coordinated Research Project on 'Examination of advanced fast reactor fuel and core structural materials. Each of the 24 presentations made at the meeting have been indexed separately

  7. 77 FR 22332 - Center for Scientific Review; Notice of Meeting

    Science.gov (United States)

    2012-04-13

    ... meeting will be open to the public with attendance limited to space available. Individuals who plan to... Advisory Committee Policy. [FR Doc. 2012-8919 Filed 4-12-12; 8:45 am] BILLING CODE 4140-01-P ...

  8. 78 FR 19497 - Center for Scientific Review; Notice of Meeting

    Science.gov (United States)

    2013-04-01

    ... meeting will be open to the public, with attendance limited to space available. Individuals who plan to..., Program Analyst, Office of Federal Advisory Committee Policy. [FR Doc. 2013-07419 Filed 3-29-13; 8:45 am...

  9. 77 FR 59202 - Center for Scientific Review; Notice of Meeting

    Science.gov (United States)

    2012-09-26

    ... meeting will be open to the public, with attendance limited to space available. Individuals who plan to... Advisory Committee Policy. [FR Doc. 2012-23624 Filed 9-25-12; 8:45 am] BILLING CODE 4140-01-P ...

  10. Internet and Audiology: A Review of the First International Meeting.

    Science.gov (United States)

    Andersson, Gerhard; Lunner, Thomas; Laplante-Lévesque, Ariane; Preminger, Jill E

    2015-09-01

    The purpose of this research forum article is to describe the impetus for holding the First International Meeting on Internet and Audiology (October 2014) and to introduce the special research forum that arose from the meeting. The rationale for the First International Meeting on Internet and Audiology is described. This is followed by a short description of the research sections and articles appearing in the special issue. Six articles consider the process of health care delivery over the Internet; this includes health care specific to hearing, tinnitus, and balance. Four articles discuss the development of effective Internet-based treatment programs. Six articles describe and evaluate Internet-based interventions specific to adult hearing aid users. The fledgling field of Internet and audiology is remarkably broad. The Second International Meeting on Internet and Audiology ocurred in September 2015.

  11. 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...

  12. 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...

  13. 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.)

  14. Review of TSOs technical needs in safety research and development

    International Nuclear Information System (INIS)

    Rintamaa, R.; Bruna, G.

    2012-01-01

    ETSON is the network of European Technical Safety Organizations. The ETSON members have elaborated together a position paper which identifies and ranks the main research and development fields of endeavor in a short, mid and long term perspective. The main research areas and major needs are grouped in 7 areas: 1) safety assessment methods, 2) multi-physics safety approach (several disciplines, macroscopic and microscopic level), 3) Ageing of materials, 4) fuel behaviour, 5) human and organisational factors, 6) instrumentation and control, 7) Severe accidents: phenomenology and methodology, and severe accidents: crisis preparedness and major needs. ETSON has coordinated the activities with other European platforms and has widely contributed to the NUGENIA (Nuclear Generation 2 and 3 Association) topic research and development areas. The next step will be a prioritization of these needs

  15. 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.

  16. Technical review of the dispersion and dose models used in the MILDOS computer program

    International Nuclear Information System (INIS)

    Horst, T.W.; Soldat, J.K.; Bander, T.J.

    1982-05-01

    The MILDOS computer code is used to estimate impacts of radioactive emissions from uranium milling facilities. This report reviews the technical basis of the models used in the MILDOS computer code. The models were compared with state-of-the-art predictions, taking into account the intended uses of the MILDOS code. Several suggested modifications are presented and the technical basis for those changes are given

  17. 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

  18. 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.

  19. 43rd Plenary Meeting Report of the Scientific, Technical and Economic Committee for Fisheries (PLEN-13-01)

    DEFF Research Database (Denmark)

    Casey, J.; Abella, J. A.; Andersen, J.

    The Scientific, Technical and Economic Committee for Fisheries hold its 43rd plenary on 8-12 July 2013 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 deal...... were inter alia assessments of the economic performance of the EU fishing fleet, fishing effort regime evaluations, future EU data collection, and review of stock advice.......The Scientific, Technical and Economic Committee for Fisheries hold its 43rd plenary on 8-12 July 2013 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...

  20. 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