WorldWideScience

Sample records for fall technical meeting

  1. Students fall for Fall Meeting

    Science.gov (United States)

    Smedley, Kara

    2012-02-01

    From Boston to Beijing, thousands of students traveled to San Francisco for the 2011 AGU Fall Meeting. Of those who participated, 183 students were able to attend thanks to AGU's student travel grant program, which assists students with travel costs and seeks to enrich the meeting through ethnic and gender diversity. Students at Fall Meeting enjoyed a variety of programs and activities designed to help them better network with their peers, learn about new fields, and disseminate their research to the interested public. More than 800 students attended AGU's first annual student mixer, sharing drinks and ideas with fellow student members and future colleagues as well as forging new friendships and intellectual relationships.

  2. 1990 Fall Meeting Report

    Science.gov (United States)

    Chapman, David S.

    The AGU 1990 Fall Meeting, held in San Francisco December 3-7, continued the steady growth trend for the western meeting set over the last decade. About 5200 members registered for the meeting and 3836 papers were given. The scientific kickoff to the meeting was provided by a Union session on initial results of the current Magellan mission to Venus. The mission was also the focus of a public lecture and short film on highlights of the mission and an extensive Union poster session.

  3. 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

  4. 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

  5. Proceedings of the Korean Society for Nondestructive Testing Fall Meeting 1993

    International Nuclear Information System (INIS)

    1993-11-01

    This proceedings contains articles of the Korean Society for Nondestructive Testing Fall Meeting, 1993. It was held on Nov. 22, 1993 in Seoul, Korea and subject of the Korean Society for Nondestructive Testing Fall Meeting 1993. There are main session and technical session.

  6. 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

  7. Proceedings of the KNS Fall meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-10-15

    This proceedings contains articles of 2013 Fall meeting of the Korean Nuclear Society. It was held on Oct 23-25 in Kyungju, Korea. This proceedings is comprised of 10 sessions. The main subject titles of session are as follows: Reactor system technology, Nuclear data, reactor physics and computational science, Radioactive waste management, Nuclear fuel and materials, Thermal hydraulics and safety, Radiation utilization and protection, Quantum engineering and nuclear fusion, Nuclear power plant construction and operation technology, Nuclear policy, human resources and cooperation, Nuclear I and C and remote operation. (Yi, J. H.)

  8. Proceedings of the KNS 2015 Fall Meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-10-15

    This proceedings contains articles of 2015 fall meeting of the Korean Nuclear Society. It was held on October 28-30 in Kyungju, Korea. This proceedings is comprised of 11 sessions. The main subject titles of session are as follows: Reactor system technology, Reactor physics and computational science, Radioactive waste management, Nuclear fuel and materials, Thermal hydraulics and safety, Radiation utilization and protection, Quantum engineering and nuclear fusion, Nuclear power plant construction and operation technology, Nuclear policy, human resources and cooperation, Nuclear I and C and automatic remote systems, Competition Session. (Yi, J. H.)

  9. Proceedings of the KNS 2014 Fall Meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-10-15

    This proceedings contains articles of 2014 Fall Meeting of the Korean Nuclear Society. It was held on Oct 29-31 in Pyongchang, Korea. This proceedings is comprised of 10 sessions. The main subject titles of session are as follows: Reactor system technology, Reactor physics and computational science, Radioactive waste management, Nuclear fuel and materials, Thermal hydraulics and safety, Radiation utilization and protection, Quantum engineering and nuclear fusion, Nuclear power plant construction and operation technology, Nuclear policy, human resources and cooperation, MMIS and remote control and Competition (Yi, J. H.)

  10. Public affairs events at Fall Meeting

    Science.gov (United States)

    Uhlenbrock, Kristan

    2012-02-01

    AGU's Public Affairs team presented two workshop luncheons and hosted 17 oral and poster sessions at the 2011 Fall Meeting. Topics ranged from defining the importance of the geosciences, to climate change science for communities and institutions. The workshop luncheon "How to Be a Congressional Science Fellow or Mass Media Fellow" was a well-attended event with more than 115 participants. The luncheon provided the opportunity for audience members to ask fellow scientists about their experiences working either in Congress or as a reporter for a news organization. For scientists looking to expand their expertise outside the academic environment, these AGU fellowships are fantastic opportunities.

  11. 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'

  12. 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)

  13. 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

  14. AGU Cinema: Festival of short science films at Fall Meeting

    Science.gov (United States)

    Harned, Douglas A.

    2012-11-01

    New technologies have revolutionized the use of video as a means of science communication and have made it easier to create, distribute, and view. With video having become omnipresent in our culture, it sometime supplements or even replaces writing in many science and education applications. An inaugural science film festival sponsored by AGU at the 2012 Fall Meeting in San Francisco, Calif., in December will showcase short videos—30 minutes or less in length—developed to disseminate scientific results to various audiences and to enhance learning in the classroom. AGU Cinema will feature professionally produced, big budget films alongside low-budget videos aimed at niche audiences and made by amateurs. The latter category includes videos made by governmental agency scientists, educators, communications specialists within scientific organizations, and Fall Meeting oral and poster presenters.

  15. Proceedings of the KSME 2009 fall annual meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    This proceedings contains articles of the KSME 2009 fall annual meeting. It was held on 4-6 Nov, 2009 in Pyeongchang, Korea. This proceedings is comprised of 10 sessions. The main subject titles of session are as follows: materials and fracture mechanics, CAE and applied mechanics, dynamics and control, fabrication and design, reliability, biotechnology, micro/nano-mechanics, thermodynamics, fluid mechanics, energy and dynamics. (Yi, J. H.)

  16. 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

  17. Science policy events at the 2012 AGU Fall Meeting

    Science.gov (United States)

    Hankin, Erik

    2012-10-01

    Are you interested in the intersection of science and policy, looking to make an impact on Capitol Hill, or concerned about the increasing number of attacks against scientists and their academic freedom? AGU Public Affairs offers many events at the 2012 Fall Meeting to assist member involvement in political processes and inform scientists of their rights and options should their research come under legal fire. Learn how you can share your science with policy makers to help inform policy at two luncheon events at the Fall Meeting. If you have ever considered working as a science expert for a member of Congress or reporting science in a mass media outlet, then you should attend the first luncheon, How to be a Congressional Science Fellow or Mass Media Fellow. The event will feature current AGU Congressional Science Fellows detailing their experiences working in Congress as well as past AGU Mass Media Fellows sharing their stories of reporting for a news organization. The luncheon will be held on Tuesday, 4 December, from 12:30 to 1:30 P.M. at the Marriott Hotel, in room Golden Gate B. In addition, current and former fellows will be available for one-on-one interactions at the AGU Marketplace from 3:30 to 4:30 P.M. on Tuesday, 4 December, through Thursday, 6 December.

  18. 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…

  19. Space Weather Research Presented at the 2007 AGU Fall Meeting

    Science.gov (United States)

    Kumar, Mohi

    2007-12-01

    AGU's 47th annual Fall Meeting, held 10-14 December 2007 in San Francisco, Calif., was the largest gathering of geoscientists in the Union's history. More than 14,600 people attended. The Space Physics and Aeronomy (SPA) sections sported excellent turnout, with more than 1300 abstracts submitted over 114 poster and oral sessions. Topics discussed that related to space weather were manifold: the nature of the Sun-Earth system revealed through newly launched satellites, observations and models of ionospheric convection, advances in the understanding of radiation belt physics, Sun-Earth coupling via energetic coupling, data management and archiving into virtual observatories, and the applications of all this research to space weather forecasting and prediction.

  20. CO2 Emissions Generated by a Fall AGU Meeting

    Science.gov (United States)

    osborn, G.; Malowany, K. S.; Samolczyk, M. A.

    2011-12-01

    The process of reporting on and discussing geophysical phenomena, including emissions of greenhouse gases, generates more greenhouse gases. At the 2010 fall meeting of the AGU, 19,175 delegates from 81 countries, including, for example, Eritrea, Nepal, and Tanzania, traveled a total of 156,000,000 km to congregate in San Francisco for five days. With data on home bases of participants provided by AGU, we estimated the CO2 emissions generated by travel and hotel stays of those participants. The majority of the emissions from the meeting resulted from air travel . In order to estimate the footprint of such travel, (a) distances from the largest airport in each country and American state (except Canada and California) to San Francisco were tabulated , (b) basic distances were converted to emissions using the TerraPass (TRX Travel Analytics) carbon calculator, (c) it was assumed that half the California participants would fly and half would drive, (d) it was assumed that half of Canadians would fly out of Toronto and half out of Vancouver, and (e) a fudge factor of 10% was added to air travel emissions to account for connecting flights made by some participants to the main airports in the respective countries (connecting flights are disproportionately significant because of high output during takeoff acceleration). Driving impacts were estimated with a Transport Direct/RAC Motoring Services calculator using a 2006 Toyota Corolla as a standard car. An average driving distance of 50 km to the departure airport, and from the airport upon return, was assumed. Train impacts were estimated using the assumption that all flying participants would take BART from SFO. Accomodation impacts were estimated using an Environmental Protection Agency calculator, an assumed average stay of 3 nights, and the assumption that 500 participants commuted from local residences or stayed with friends. The above assumptions lead to an estimate, which we consider conservative, of 19 million kg of

  1. Falls and Fall-Prevention in Older Persons: Geriatrics Meets Spaceflight!

    Science.gov (United States)

    Goswami, Nandu

    2017-01-01

    This paper provides a general overview of key physiological consequences of microgravity experienced during spaceflight and of important parallels and connections to the physiology of aging. Microgravity during spaceflight influences cardiovascular function, cerebral autoregulation, musculoskeletal, and sensorimotor system performance. A great deal of research has been carried out to understand these influences and to provide countermeasures to reduce the observed negative consequences of microgravity on physiological function. Such research can inform and be informed by research related to physiological changes and the deterioration of physiological function due to aging. For example, head-down bedrest is used as a model to study effects of spaceflight deconditioning due to reduced gravity. As hospitalized older persons spend up to 80% of their time in bed, the deconditioning effects of bedrest confinement on physiological functions and parallels with spaceflight deconditioning can be exploited to understand and combat both variations of deconditioning. Deconditioning due to bed confinement in older persons can contribute to a downward spiral of increasing frailty, orthostatic intolerance, falls, and fall-related injury. As astronauts in space spend substantial amounts of time carrying out exercise training to counteract the microgravity-induced deconditioning and to counteract orthostatic intolerance on return to Earth, it is logical to suggest some of these interventions for bed-confined older persons. Synthesizing knowledge regarding deconditioning due to reduced gravitational stress in space and deconditioning during bed confinement allows for a more comprehensive approach that can incorporate aspects such as (mal-) nutrition, muscle strength and function, cardiovascular (de-) conditioning, and cardio-postural interactions. The impact of such integration can provide new insights and lead to methods of value for both space medicine and geriatrics (Geriatrics

  2. Falls and Fall-Prevention in Older Persons: Geriatrics Meets Spaceflight!

    Directory of Open Access Journals (Sweden)

    Nandu Goswami

    2017-10-01

    Full Text Available This paper provides a general overview of key physiological consequences of microgravity experienced during spaceflight and of important parallels and connections to the physiology of aging. Microgravity during spaceflight influences cardiovascular function, cerebral autoregulation, musculoskeletal, and sensorimotor system performance. A great deal of research has been carried out to understand these influences and to provide countermeasures to reduce the observed negative consequences of microgravity on physiological function. Such research can inform and be informed by research related to physiological changes and the deterioration of physiological function due to aging. For example, head-down bedrest is used as a model to study effects of spaceflight deconditioning due to reduced gravity. As hospitalized older persons spend up to 80% of their time in bed, the deconditioning effects of bedrest confinement on physiological functions and parallels with spaceflight deconditioning can be exploited to understand and combat both variations of deconditioning. Deconditioning due to bed confinement in older persons can contribute to a downward spiral of increasing frailty, orthostatic intolerance, falls, and fall-related injury. As astronauts in space spend substantial amounts of time carrying out exercise training to counteract the microgravity-induced deconditioning and to counteract orthostatic intolerance on return to Earth, it is logical to suggest some of these interventions for bed-confined older persons. Synthesizing knowledge regarding deconditioning due to reduced gravitational stress in space and deconditioning during bed confinement allows for a more comprehensive approach that can incorporate aspects such as (mal- nutrition, muscle strength and function, cardiovascular (de- conditioning, and cardio-postural interactions. The impact of such integration can provide new insights and lead to methods of value for both space medicine and

  3. Al Gore attends Fall Meeting session on Earth observing satellite

    Science.gov (United States)

    Richman, Barbara T.

    2011-12-01

    Former U.S. vice president Al Gore, making unscheduled remarks at an AGU Fall Meeting session, said, "The reason you see so many pictures" of the Deep Space Climate Observatory (DSCOVR) satellite at this session is "that it already has been built." However, "because one of its primary missions was to help document global warming, it was canceled. So for those who are interested in struggling against political influence," Gore said, "the benefits have been documented well here." Gore made his comments after the third oral presentation at the 8 December session entitled "Earth Observations From the L1 (Lagrangian Point No. 1)," which focused on the capabilities of and progress on refurbishing DSCOVR. The satellite, formerly called Triana, had been proposed by Gore in 1998 to collect climate data. Although Triana was built, it was never launched: Congress mandated that before the satellite could be sent into space the National Academies of Science needed to confirm that the science it would be doing was worthwhile. By the time the scientific validation was complete, the satellite "was no longer compatible with the space shuttle manifest," Robert C. Smith, program manager for strategic integration at the NASA Goddard Space Flight Center, told Eos.

  4. Proceedings of the Conference and Symposium Korean Association for Radiation Protection Fall Meeting 2011

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-11-15

    This proceedings contains articles of the Korean Association for Radiation Protection Fall Meeting, 2011. It was held on Nov.17-18, 2011 the ocean resort in Yeosu, Korea and subject of the Korean Association for Radiation Protection Fall Meeting 2011. This proceedings is comprised of 14 sessions.

  5. Proceedings of the Korean Society for Nondestructive Testing Fall Meeting 1999

    International Nuclear Information System (INIS)

    1999-11-01

    This proceedings contains articles of the Korean Society for Nondestructive Testing Fall Meeting, 1999. It was held on Nov. 26, 1999 in Seoul, Korea and subject of the Korean Society for Nondestructive Testing Fall Meeting 1999. This proceedings is comprised of 4 sessions.

  6. 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)

  7. 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)

  8. 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.

  9. Proceedings of the Conference and Symposium Korean Association for Radiation Protection Fall Meeting 2016

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2016-12-15

    This proceedings contains articles of the Korean Association for Radiation Protection Fall Meeting, 2016. It was held on Dec. 1, 2016 Phoenix Island in Jeju, Korea and subject of the Korean Association for Radiation Protection Fall Meeting 2016. This proceedings is comprised of 5 sessions. The main topic titles of session are as follows: Radiation protection, Biotechnology of radiation, Radiation measurement, Radiation environment and prevention, Radiation epidemiography.

  10. 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.

  11. 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)

  12. 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

  13. 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

  14. Proceedings of the Conference and Symposium Korean Association for Radiation Protection Fall Meeting 2012

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-11-15

    This proceedings contains articles of the Korean Association for Radiation Protection Fall Meeting, 2012. It was held on Nov. 28-30, 2012 Phoenix Island in Jeju, Korea and subject of the Korean Association for Radiation Protection Fall Meeting 2012. This proceedings is comprised of 8 sessions. The main topic titles of session are as follows: The main topic titles of session are as follows: Medical treatment and Biology 1, Measurement and Analysis 1, Measurement and Analysis 2, Radiation protection 1, Radiation protection 2, Medical treatment and Biology 2, Measurement and Analysis 3, Radiation protection 3.

  15. Proceedings of the Conference and Symposium Korean Association for Radiation Protection Fall Meeting 2014

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-11-15

    This proceedings contains articles of the Korean Association for Radiation Protection Fall Meeting, 2014. It was held on Nov.19-21, 2014 in Jeju, Korea and subject of the Korean Association for Radiation Protection Fall Meeting 2014. This proceedings is comprised of 8 sessions. The main topic titles of session are as follows: Radiation protection 1, Medical treatment and Biology 1, Radiation measurement 1, Radiation environment and protection 1, Radiation protection 2, Medical treatment and Biology 2, Radiation Measurement 2, Radiation environment and protection 2.

  16. Proceedings of the Conference and Symposium Korean Association for Radiation Protection Fall Meeting 2015

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-10-15

    This proceedings contains articles of the Korean Association for Radiation Protection Fall Meeting, 2015. It was held on Oct.23, 2015 Mayfield Hotel in Seoul, Korea and subject of the Korean Association for Radiation Protection Fall Meeting 2015. This proceedings is comprised of 8 sessions. The main topic titles of session are as follows: Radiation protection 1, Medical treatment and Biology 1, Radiation Measurement 1, Radiation environment and disasters prevention 1, Radiation protection 2, Medical treatment and Biology 2, Radiation Measurement 2, Radiation environment and disasters prevention 2.

  17. Proceedings of the Conference and Symposium Korean Association for Radiation Protection Fall Meeting 2013

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-11-15

    This proceedings contains articles of the Korean Association for Radiation Protection Fall Meeting, 2013. It was held on Nov.20-22, 2013 Ramada Plaza Hotel in Suwon, Korea and subject of the Korean Association for Radiation Protection Fall Meeting 2013. This proceedings is comprised of 7 sessions. The main topic titles of session are as follows: Medical treatment and Biology 1, Measurement and Analysis 1, Radiation protection1, Medical treatment and Biology 2, Measurement and Analysis 2, Radiation protection 2, Radiation protection 3.

  18. 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.

  19. 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

  20. 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)

  1. 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

  2. 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

  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. 76 FR 59125 - 2011 Fall Meeting of the Ozone Transport Commission

    Science.gov (United States)

    2011-09-23

    ..., Washington, DC 20001; (202) 508-3840; e-mail: [email protected] ; Web site: http://www.otcair.org...) 508-3840; by e-mail: [email protected] or via the OTC Web site at http://www.otcair.org . Dated... ENVIRONMENTAL PROTECTION AGENCY [FRL-9470-8] 2011 Fall Meeting of the Ozone Transport Commission...

  5. 75 FR 58378 - 2010 Fall Meeting of the Ozone Transport Commission

    Science.gov (United States)

    2010-09-24

    ..., Washington, DC 20001; (202) 508-3840; e-mail: [email protected] ; Web site: http://www.otcair.org...) 508-3840; by e-mail: [email protected] or via the OTC Web site at http://www.otcair.org . Dated... ENVIRONMENTAL PROTECTION AGENCY [FRL-9206-6] 2010 Fall Meeting of the Ozone Transport Commission...

  6. SIAM 1978 fall meeting and symposium on sparse matrix computations. [Knoxville, Tenn. , October 30--November 3

    Energy Technology Data Exchange (ETDEWEB)

    1978-01-01

    The program and abstracts of the SIAM 1978 fall meeting in Knoxville, Tennessee, are given, along with those of the associated symposium on sparse matrix computations. The papers dealt with both pure mathematics and mathematics applied to many different subject areas. (RWR)

  7. 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.)

  8. 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.)

  9. 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)

  10. 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.)

  11. 77 FR 65380 - 2012 Fall Joint Meeting of the Ozone Transport Commission and the Mid-Atlantic Northeast...

    Science.gov (United States)

    2012-10-26

    ... ENVIRONMENTAL PROTECTION AGENCY [FRL-9745-9] 2012 Fall Joint Meeting of the Ozone Transport Commission and the Mid-Atlantic Northeast Visibility Union AGENCY: Environmental Protection Agency (EPA... Fall Meeting of the Ozone Transport Commission (OTC) and the Mid-Atlantic Northeast Visibility Union...

  12. Standard technical specifications for Westinghouse pressurized water reactors (revision issued Fall 1981). Technical report

    International Nuclear Information System (INIS)

    Virgilio, M.J.

    1981-11-01

    The Standard Technical Specifications for Westinghouse Pressurized Water Reactors (W-STS) is a generic document prepared by the U.S. NRC for use in the licensing process of current Westinghouse Pressurized Water Reactors. The W-STS sets forth the Limits, Operating Conditions and other requirements applicable to nuclear reactor facility operation as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

  13. 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

  14. Fall

    OpenAIRE

    Odundo, Magdalene

    2008-01-01

    The monoprint Fall, created in the artist-in-residence studio at Dartmouth College, Hanover, New England, represents a transient yet vivid memory of the season spent walking and re-walking a trail I took to the studio on a daily basis. The work arose spontaneously from a direct and instinctive wish to replicate the ghost imprints left on the trail by the wet and dry weather of that autumn. It also represented a sensationally hopeful political transition of what seemed to be the growth of hope...

  15. Results from Consultancy Meeting on Qualified Technical Centres

    International Nuclear Information System (INIS)

    Novakovic, Mladen

    2017-01-01

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

  16. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-12-01

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

  18. 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.

  19. 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)

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

    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)

  1. 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...

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

    International Nuclear Information System (INIS)

    2002-07-01

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

  3. 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

  4. 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...

  5. 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...

  6. 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...

  7. 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...

  8. 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...

  9. 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...

  10. 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...

  11. 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...

  12. 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...

  13. 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...

  14. 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...

  15. 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...

  16. 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...

  17. 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...

  18. 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...

  19. 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...

  20. 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...

  1. 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...

  2. 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...

  3. 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...

  4. 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...

  5. 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...

  6. 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...

  7. 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...

  8. 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...

  9. Symposium on the Physical Chemistry of Solar Energy Conversion, Indianapolis American Chemical Society Meetings, Fall 2013

    Energy Technology Data Exchange (ETDEWEB)

    Lian, Tianquan [PI, Emory Univ.

    2013-09-20

    The Symposium on the Physical Chemistry of Solar Energy Conversion at the Fall ACS Meeting in Indianapolis, IN (Sept. 8-12) featured the following sessions (approx. 6 speakers per session): (1) Quantum Dots and Nanorods for Solar Energy Conversion (2 half-day sessions); (2) Artificial Photosynthesis: Water Oxidation; (3) Artificial Photosynthesis: Solar Fuels (2 half-day sessions); (4) Organic Solar Cells; (5) Novel Concepts for Solar Energy Conversion (2 half-day sessions); (6) Emerging Techniques for Solar Energy Conversion; (7) Interfacial Electron Transfer

  10. How Science and Hollywood Can Work Together Is Focus of Fall Meeting Panel

    Science.gov (United States)

    Showstack, Randy

    2011-01-01

    Jon Amiel, director of the 2003 science fiction blockbuster movie The Core, told a room packed with geophysicists at the recent AGU Fall Meeting that he had a confession to make. The confession had nothing to do with what he called the “preposterous premises” of the movie, including that humans could start or stop the spinning of Earth's core. Rather, he told the crowd at the Tuesday evening presentation “Science and the Cinema: AGU Sciences Meet Hollywood” about his recurring dream of being on stage wearing nothing but a skimpy T-shirt. “This dream now has come true. Here I am, I'm talking to a whole room of geophysicists about The Core. I've never felt like the T-shirt was this short,” he said.

  11. 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

  12. 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

  13. 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)

  14. 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

  15. 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.

  16. 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

  17. 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

  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. Videos, tweet-ups, and training unite scientist communicators at Fall Meeting

    Science.gov (United States)

    Adams, Mary Catherine; Ramsayer, Kate

    2012-02-01

    AGU's public information office held several events at the 2011 Fall Meeting designed to train, recognize, and reward member scientists who communicate with, or want to communicate with, nonscience audiences. On Sunday, about 90 researchers gathered at the Marriott Marquis hotel for an all-day science communications training event covering topics including journalism from the insider's perspective, storytelling, and using humor to share science. On Wednesday a communications panel focusing specifically on climate science shared tips on communicating with audiences via TV and the Web, among other outlets. At a social media soiree Monday evening, geobloggers, Facebook fans, Twitter followers, and others met in person and talked about how to share news and research across the many platforms of the Internet. Later in the week, bloggers from AGU's blogosphere and other sites met for lunch to discuss the online Earth and space science community.

  20. 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)

  1. 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

  2. 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.

  3. 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)

  4. 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)

  5. 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)

  6. 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)

  7. 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)

  8. 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)

  9. 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)

  10. 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

  11. 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

  12. 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...

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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.

  20. 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

  1. 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...

  2. 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

  3. 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...

  4. 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...

  5. 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)

  6. 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)

  7. 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.)

  8. 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)

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

    International Nuclear Information System (INIS)

    Otsuka, Naohiko

    2012-06-01

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

  10. 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)

  11. 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)

  12. 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)

  13. 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)

  14. 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)

  15. 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.

  16. 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)

  17. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    Blanton, J.M.

    1992-10-01

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

  19. 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

  20. 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

  1. 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...

  2. 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.

  3. Local Normative Data on easyCBM[R] Reading and Mathematics: Fall 2009. Technical Report # 0918

    Science.gov (United States)

    Tindal, Gerald; Alonzo, Julie; Anderson, Daniel

    2009-01-01

    We developed equivalent, alternate forms of easyCBM[R] in reading (n=20 forms) and mathematics (n=13 forms) with different skills reflective of the National Reading Panel (NRP) and the National Council of Teachers of Mathematics (NCTM), respectively. We then took three forms to use as screening measures in the fall, winter, and spring so educators…

  4. 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

  5. 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)

  6. 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

  7. 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

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

    International Nuclear Information System (INIS)

    2001-05-01

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

  9. 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

  10. 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)

  11. 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

  12. 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.

  13. 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

  14. [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)

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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...

  20. 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

  1. 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.

  2. 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

  3. Proceedings of the Korean Society for Nondestructive Testing Fall Meeting 1998

    International Nuclear Information System (INIS)

    1998-05-01

    This proceedings contains articles of the Korean Society for Nondestructive Testing Spring Meeting, 1998. It was held on May.8-9, 1998 Yeungnam University in Daegu, Korea and subject of the Korean Society for Nondestructive Testing Spring Meeting 1998. This proceedings is comprised of 4 sessions.

  4. 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

  5. BMFT-CEA-US-DOE Exchange on KNK II-Rapsodie-EBR II operating experience, German contributions for the second expert meeting at Idaho Falls, USA, October 27 and 28, 1982

    International Nuclear Information System (INIS)

    1982-10-01

    The meeting at Idaho Falls was the follow-up meeting of the first expert meeting on EBR II- Rapsodie- KNK II operating experience, which took place at the Karlsruhe Research Center in March 1980. The present report compiles the ten German papers presented at the Idaho Falls meeting, discussing various aspects of experience gained by the operation of KNK II

  6. 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

  7. 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)

  8. 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)

  9. 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)

  10. 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

  11. 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

  12. 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

  13. 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)

  14. 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

  15. 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.)

  16. 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)

  17. 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.)

  18. 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.

  19. 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)

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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.

  5. 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)

  6. 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.

  7. 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)

  8. 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

  9. 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)

  10. 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

  11. 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

  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. 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

  15. 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

  16. 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

  17. 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)

  18. 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.

  19. 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

  20. 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

  1. 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

  2. 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)

  3. 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

  4. 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)

  5. 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

  6. 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

  7. 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

  8. 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

  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. The AGU Hydrology Student Subcommittee (H3S) - fostering the Fall Meeting experience for young hydrologists

    Science.gov (United States)

    Claes, N.; Beria, H.; Brown, M. R. M.; Kumar, A.; Goodwell, A. E.; Preziosi-Ribero, A.; Morris, C. K.; Cheng, F. Y.; Gootman, K. S.; Welsh, M.; Khatami, S.; Knoben, W.

    2017-12-01

    The AGU Hydrology Section Student Subcommittee (H3S), the student body of the AGU hydrology section, caters to the needs of students and early career scientists whose research interests contain a hydrological component. The past two years, H3S organized a Student and Early Career Scientist conference addressing both the technical and research needs of young hydrologists. Over the past several years, H3S organized pop-up sessions in Water Sciences and Social Dimensions of Geosciences which allowed young hydrologists to share and learn from their collective experiences. Social events like the early career social mixer, co-organized with CUAHSI, led to increased networking opportunities among peers. Continuous social media engagement led to a general dialogue within the community over varied issues including research productivity, gender equality, etc. Ice-breaker events between junior and senior academics encouraged young hydrologists to talk with their academic crushes and continuously seek out mentorship opportunities. Collating our past experiences, we ponder over our accomplishments, failures, and opportunities to improve representation of early career hydrologists within the community.

  11. Carbon Capture Multidisciplinary Simulation Center Trilab Support Team (TST) Fall Meeting 2016 Report

    Energy Technology Data Exchange (ETDEWEB)

    Draeger, Erik W. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-01-03

    The theme of this year’s meeting was “Predictivity: Now and in the Future”. After welcoming remarks, Erik Draeger gave a talk on the NNSA Labs’ history of predictive simulation and the new challenges faced by upcoming architecture changes. He described an example where the volume of analysis data produced by a set of inertial confinement fusion (ICF) simulations on the Trinity machine was too large to store or transfer, and the steps needed to reduce it to a manageable size. He also described the software re-engineering plan for LLNL’s suite of multiphysics codes and physics packages with a new push toward common components, making collaboration with teams like the CCMSC who already have experience trying to architect complex multiphysics code infrastructure on next-generation architectures all the more important. Phil Smith then gave an overview outlining the goals of the project, namely to accelerate development of new technology in the form of high efficiency carbon capture pulverized coal power generation as well as further optimize existing state of the art designs. He then presented a summary of the Center’s top-down uncertainty quantification approach, in which ultimate target predictivity informs uncertainty targets for lower-level components, and gave data on how close all the different components currently are to their targets. Most components still need an approximately two-fold reduction in uncertainty to hit the ultimate predictivity target, but the current accuracy is already rather impressive.

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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.

  17. 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

  18. 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

  19. 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)

  20. 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)

  1. 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

  2. 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)

  3. 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

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

    International Nuclear Information System (INIS)

    2001-08-01

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

  5. 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)

  6. 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.

  7. 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.

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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)

  13. 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.

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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...

  3. 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

  4. 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.

  5. 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

  6. 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)

  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. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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.

  18. 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

  19. 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

  20. 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

  1. 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.

  2. 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)

  3. 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)

  4. 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

  5. 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)

  6. 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...

  7. 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...

  8. 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...

  9. 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

  10. 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

  11. 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

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

    International Nuclear Information System (INIS)

    2011-01-01

    concepts incorporating innovative systems and components, as well as advanced fuel and fuel cycle technologies. In particular, innovative heat exchangers and steam generators are key to significanly reduce the capital cost of the NSSS of the fast reactors. The IAEA, within the framework of its Nuclear Energy Department’s Technical Working Group on Fast Reactors (TWG-FR), assists Member States activities in these 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)]. This topical TM is addressing Member States’ expressed information exchange needs in the field of advanced fast reactor design features, with particular attention to innovative heat exchangers and steam generators

  13. 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)

  14. 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.)

  15. 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.)

  16. 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

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

    International Nuclear Information System (INIS)

    2000-02-01

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

  18. 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.

  19. 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

  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. 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)

  2. 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

  3. 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)

  4. 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.

  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. 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

  11. 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

  12. 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

  13. 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

  14. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    Janev, R K

    1999-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-12-01

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

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

    International Nuclear Information System (INIS)

    Janev, R.K.

    1999-05-01

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

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

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  19. 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

  20. 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

  1. 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.

  2. 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...

  3. 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.)

  4. Proceedings of the Tri-Service Aeromedical Research Panel Fall Technical Meeting, 13-14 November 1984.

    Science.gov (United States)

    1984-11-01

    and is related to the spherical aberration just described in an interesting way. In providing an ophthalmic correction for ametropia , the convention...revealed that 20% of the pilots and 50% of the navigators wore corrective lenses. This trend towards ametropia in pilots is apparently increasing

  5. 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)

  6. 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

  7. 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

  8. 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...

  9. 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...

  10. 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…

  11. 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

  12. 78 FR 54644 - 2013 Fall Joint Meeting of the Ozone Transport Commission and the Mid-Atlantic Northeast...

    Science.gov (United States)

    2013-09-05

    ... Transport Commission and the Mid-Atlantic Northeast Visibility Union AGENCY: Environmental Protection Agency...-Atlantic Northeast Visibility Union (MANE-VU). The meeting agenda will include topics regarding reducing...-level ozone formation, transport, and control within the OTR. The Mid-Atlantic/Northeast Visibility...

  13. 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...

  14. 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.)

  15. 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.

  16. 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.

  17. 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

  18. 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

  19. 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.

  20. 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);…

  1. 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

  2. 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.

  3. 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.

  4. 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.

  5. 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...

  6. 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...

  7. 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

  8. Preprint of the Fall 1997 JSAE (Japan Society of Automotive Engineers) Meeting Science Lecture. No. 974; Jidosha gijutsukai 1997 nen shuki taikai gakujutsu koenkai maezurishu. 974

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

    This is a comprehensive compilation of 66 papers made public in the Fall 1997 JSAE Meeting, including the following by field: 13 papers on engine combustion; 4 on analysis of chassis structure; 12 on travel of vehicles; 6 on improvement of exhaust gas from diesel engines; 9 on basic study of combustion characteristics using fuels such as methanol, natural gas and hydrogen; 3 on study of heat flux on the piston face of internal engines; others on processing technology, noise, etc. Among these, the following were paid attention to as studies aiming at reducing NOx and smoke of diesel engines for pollution prevention: Emission and combustion characteristics of multiple stage diesel combustion, and Study on homogeneous charge diesel combustion engine. As studies on the use of petroleum substituting fuels, Visualizing ignition and combustion of methanol mixtures in a diesel engine, Improving performance and emissions in a diesel engine dual-fueled with natural gas, and Fundamental combustion characteristics of lean hydrogen mixtures

  9. Preprint of the Fall 1997 JSAE (Japan Society of Automotive Engineers) Meeting Science Lecture. No. 976; Jidosha gijutsukai 1997 nen shuki taikai gakujutsu koenkai maezurishu. 976

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

    The Fall 1997 JSAE Meeting Science Lecture was held in Hiroshima on October 21-23, 1997. This report summarized 90 out of the total 244 lectures. As for reports on gasoline engines, the following were included: Effects of fuel and air mixing on WOT output in direct injection gasoline engine, Mixture formation of direct gasoline injection engine, etc. As to sensors, Study of a fuel injection quantity sensor in diesel engine, Development of air fuel ratio sensor, etc. Concerning automotive parts, Prediction and optimization of friction characteristics of brake pads, The new conceptual copper alloy bearing for diesel engine to achieve longer life under higher load, A study of improvement in 1st ring`s gas-seal, etc. In relation to driving, accidents, etc., Effects of cellular telephone manipulation on driver`s performance, Study on traffic accidents mechanism with automatic recording systems, etc

  10. 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.

  11. 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

  12. 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

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

    International Nuclear Information System (INIS)

    2009-01-01

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

  14. 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

  15. 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

  16. Special issue containing papers presented at the 12th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems (7-11 September 2011) Special issue containing papers presented at the 12th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems (7-11 September 2011)

    Science.gov (United States)

    Berk, H. L.

    2012-09-01

    addition, a significant number of studies focused on understanding nonlinear behaviour by means of computer simulation of energetic particle driven instability. An under-represented area of investigation was the study of electron runaway formation during major tokamak disruptions. It was noted in an overview by S. Putvinski that electron energies in the 10-20 MeV range is to be expected during projected major disruptions in ITER and that reliable methods for mitigation of the runaway process needs to be developed. Significant recent work in the field of the disruption induced electron runaway, which was reported by J. Riemann, does not appear in this special issue of Nuclear Fusion as the work had been previously submitted to Physics of Plasmas [3]. Overall it is clear that reliable mitigation of electron runaway is an extremely important topic that is in need of better understanding and solutions. It has been my pleasure to serve as the organizer of the 12th meeting and to serve as a Guest Editor of this issue of Nuclear Fusion. I am sure that the contents of this issue will serve as a valuable research guide to the field of energetic particle behaviour in a burning plasma for many years to come. The site of the next meeting will by Beijing, China in the fall of 2013, which will be organized by Zinghong Lin. References [1] Program 2011 12th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems (Austin, Texas, USA, 7-11 September 2011) http://w3fusion.ph.utexas.edu/ifs/iaeaep/program.html [2] Program 2011 5th IAEA Technical Meeting on Theory of Plasma Wave Instabilities (Austin, Texas, USA, 5-7 September 2011) http://w3fusion.ph.utexas.edu/ifs/iaeapi/program.html [3] Riemann J., Smith H.M. and Helander P. 2012 Phys. Plasmas 19 012507

  17. 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.

  18. 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

  19. 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

  20. 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

  1. 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)

  2. 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...

  3. 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.

  4. 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...

  5. 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

  6. 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...

  7. 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...

  8. 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...

  9. 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...

  10. 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...

  11. 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...

  12. 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...

  13. 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...

  14. 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.

  15. 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

  16. [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

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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;

  2. 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.

  3. 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

  4. 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

  5. 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.

  6. 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)

  7. 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

  8. 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

  9. 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)

  10. 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

  11. What do computer worlds tell us about changes to rain and falling ice-water in the state where this meeting is usually held?

    Science.gov (United States)

    Langenbrunner, B.

    2017-12-01

    To learn how the world will change because of human-caused warming, we use computer-made worlds that couple land, water, and air to study their responses to the causes of warming over many years. For changes to rain and falling ice-water, these computer worlds are great at answering questions about very large places, like big areas of land or water, but they are not as good when thinking about more focused areas, like cities or states. This is especially true in the state where this meeting happens most years; will it be wetter or drier by the year 2100, and by how much? I will talk about the work being done to learn why these computer worlds do not always agree, as well as the work that finds changes on which they do agree. One big reason they don't agree is because these computer worlds arrive at different guesses on how winds will shift high up in the air in cooler months. These winds will push rain and falling ice-water to different places up and down the state over time, making it hard to know what we can expect, though our best guess is that it will be ever-so-slightly wetter. Computer worlds do agree, however, on two important things across most of the state: that the very largest bursts of rain will happen more often as the world warms, and that more often, very wet years will follow very dry years immediately before them. Taken together, these changes are important to the those in the state who plan for up-coming water needs. Knowing how normal rain and ice-water will change is part of the story, but perhaps more important is understanding how the very biggest showers are shifting, which will help the state plan for and handle these more sudden (and serious) bursts of water.

  12. 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.)

  13. 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

  14. 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

  15. 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

  16. 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

  17. Fuel cycle options for light water reactors and heavy water reactors. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1999-11-01

    In the second half of the 20th century nuclear power has evolved from the research and development environment to an industry that supplies 16% of the world's electricity. By the end of 1997, over 8500 reactor-years of operating experience had been accumulated. Global environmental change, and the continuing increase in global energy supply required to provide increasing populations with an improving standard of living, make the contribution from nuclear energy even more important for the next century. For nuclear power to achieve its full potential and make its needed contribution, it must be safe, economical, reliable and sustainable. All of these factors can be enhanced by judicious choice and development of advanced fuel cycle options. The Technical Committee Meeting (TCM) on Fuel Cycle Options for Light Water Reactors and Heavy Water Reactors was hosted by Atomic Energy of Canada Limited (AECL) on behalf of the Canadian Government and was jointly conducted within the frame of activities of the IAEA International Working Group on Advanced Technologies for Light Water Reactors (IWG-LWR) and the IAEA International Working Group on Advanced Technologies for Heavy Water Reactors (IWG-HWR). The TCM provided the opportunity to have in-depth discussions on important technical topics which were highlighted in the International Symposium on Nuclear Fuel Cycle and Reactor Strategies: Adjusting to New Realities, held in Vienna, 3-6 June 1997. The main results and conclusions of the TCM were presented as input for discussion at the first meeting of the IAEA newly formed International Working Group on Fuel Cycle Options

  18. Meeting

    Indian Academy of Sciences (India)

    energy is becoming less important in shaping economic growth ... making more efficient use of energy, it becomes possible to ... speech that Professor Raman gave at the Science. Congress held at ... as free from technicalities as possible, a general account of the ..... end to end as in surface films of long-chain fatty acids.

  19. Preprint of the Fall 1996 Meeting of the Society of Naval Architects of Japan; Nippon zosen gakkai (1996 nen) shuki koen ronbun maezuri

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    Among the papers made public in the Fall 1996 Meeting of the Society of Naval Architects of Japan, 35 papers pertaining to structure, materials, welding, construction and design were summed up as the second book. Concerning structure and materials relations, the book included papers titled An elasto-plastic analysis and the resisting mechanism during large deflection of thin shell structures; Collapse behaviour of stiffened plating under thrust; Post-yield behavior of ship plates; Strength of aluminum alloy members for hull structures; etc. With relation to welding and construction relations, Fatigue strength evaluation method using local and structural stress concentration factors for weld toe of welded joint; Practical evaluation of CTOD for highly strain concentrated structural components; Evaluation of HAZ fracture toughness of welded joints with strength mis-matching by the local approach; etc. As to the design relation, A study of structural optimization design system based on product model in shipbuilding; Basic studies on design supporting system of offshore structures; etc.

  20. Preprint of the Fall 1996 Meeting of the Society of Naval Architects of Japan; Nippon zosen gakkai (1996 nen) shuki koen ronbun maezuri

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    Among the papers made public in the Fall 1996 Meeting of the Society of Naval Architects of Japan, 35 papers pertaining to structure, materials, welding, construction and design were summed up as the second book. Concerning structure and materials relations, the book included papers titled An elasto-plastic analysis and the resisting mechanism during large deflection of thin shell structures; Collapse behaviour of stiffened plating under thrust; Post-yield behavior of ship plates; Strength of aluminum alloy members for hull structures; etc. With relation to welding and construction relations, Fatigue strength evaluation method using local and structural stress concentration factors for weld toe of welded joint; Practical evaluation of CTOD for highly strain concentrated structural components; Evaluation of HAZ fracture toughness of welded joints with strength mis-matching by the local approach; etc. As to the design relation, A study of structural optimization design system based on product model in shipbuilding; Basic studies on design supporting system of offshore structures; etc.

  1. Preprint of the Fall 1996 Meeting of the Society of Naval Architects of Japan; Nippon zosen gakkai (1996 nen) shuki koen ronbun maezuri

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    Among the papers made public in the Fall 1996 Meeting of the Society of Naval Architects of Japan, 40 papers pertaining to resistance, propulsion, motion, and ocean were summed up as the first book. Concerning the resistance relation, the book included papers titled Analysis of wave-making characteristics of ship form by Mathieu function expansions of wave-amplitude functions derived from wave analysis; Studies on surface tension effect on free surface flow around floating models; Numerical computation of viscous flows with free surface around a series 60 model; etc. As to the propulsion and motion, Design system for optimum contra-rotating propellers; Performance of the patrol icebreaker `TESHIO` in ice-covered waters; A study on effect of bow shape on icebreaking resistance; Time domain analysis of ship response in directional irregular wave; Study on prediction method for hydrodynamic force acting on a ship hull in swaying motion; etc. With relation to the ocean relation, On statistical properties of wave amplitudes in stormy sea; Statistical properties of encounter wave grouping phenomena in following and quartering seas; Development of hybrid type on board measuring system for directional wave spectrum; etc.

  2. 1996 Fall Meeting of JSAE (Japan Society of Automotive Engineers). Preprint of the academic lecture (No. 965); JSAE 1996 nendo shuki taikai. Gakujutsu koenkai maezurishu (No.965)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    The JSAE 1996 Fall Meeting was held in Sapporo during October 22-24, and 232 papers were reported. As for the vehicle safety in collision, a lot of papers were made public including the ones having the following titles: Study on vehicle body structure at frontal collision; Study on the load-stress simulation method for vehicle structure; High strain rate deformation behavior of steel sheet for automotive anti-collision parts; Optimization of the crush characteristic of door inner material for occupant injury in side impact. As to the measurement relation, the following were reported: Development of three-dimensional dynamic clearance and interference evaluation method for engine with video measurement; Proposal for a new laboratory automation standard IMACS96; Small gas samples analyzed for NOx by electron capture detector; Mechanism analysis of shock absorber rattling noise; etc. With relation to the catalytic system, reported were Study on electrically heated catalyst (EHC) system; Development of NOx removal catalysts for lean-burn gasoline engines; Study on the applicability of three-way catalyst system to medium/heavy duty gasoline trucks; etc.

  3. Preprint of the Fall 1996 Meeting of the Society of Naval Architects of Japan; Nippon zosen gakkai (1996 nen) shuki koen ronbun maezuri

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    Among the papers made public in the Fall 1996 Meeting of the Society of Naval Architects of Japan, 40 papers pertaining to resistance, propulsion, motion, and ocean were summed up as the first book. Concerning the resistance relation, the book included papers titled Analysis of wave-making characteristics of ship form by Mathieu function expansions of wave-amplitude functions derived from wave analysis; Studies on surface tension effect on free surface flow around floating models; Numerical computation of viscous flows with free surface around a series 60 model; etc. As to the propulsion and motion, Design system for optimum contra-rotating propellers; Performance of the patrol icebreaker `TESHIO` in ice-covered waters; A study on effect of bow shape on icebreaking resistance; Time domain analysis of ship response in directional irregular wave; Study on prediction method for hydrodynamic force acting on a ship hull in swaying motion; etc. With relation to the ocean relation, On statistical properties of wave amplitudes in stormy sea; Statistical properties of encounter wave grouping phenomena in following and quartering seas; Development of hybrid type on board measuring system for directional wave spectrum; etc.

  4. 1996 Fall Meeting of JSAE (Japan Society of Automotive Engineers). Preprint of the academic Lecture (No.964); JSAE 1996 nen shuki taikai. Gakujutsu koenkai maezurishu (No.964)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    The JSAE 1996 Fall Meeting was held in Sapporo during October 22-14, and 232 papers were reported. As for the aerodynamic relation of automobiles, a lot of papers were made public including the ones titled as follows: Measurement of automobile aerodynamic noise in wind tunnels; Estimation and reduction of aerodynamic noise by motorcycle scale model testing; flow visualization around door mirror thinking about adhesion of raindrops and wind noise; The aerodynamic interferences on a vehicle caused by another different length vehicle in tandem driving. As to the driving behavior, the following were reported: The influence of automatic vehicle control algorithm on traffic flow; Analysis of the benefits of freight consolidation in auto parts delivery; The development of simulation model of the driver`s behavior upon which a car was parked; etc. With relation to the control system, lots of papers were read including the following: Brake force distribution control system using hydraulic actuator; The effect of 4ws with H{sup infinity} control system theory in comparison with conventional 4ws; An adaptive LQ control system design for front and rear wheel steering vehicle.

  5. 1996 Fall Meeting of JSAE (Japan Society of Automotive Engineers). Preprint of the academic lecture (No. 966); JSAE 1996 nendo shuki taikai. Gakujutsu koenkai maezurishu (No.966)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    The JSAE 1996 Fall Meeting was held in Sapporo during October 22-24, and 232 papers were reported. As for the lubricating oil, the papers with the following titles were made public: Influence of engine oil viscosity and friction modifiers on coefficients of friction; Study on diesel fuel lubricity; Effect of diesel fuel components on lubricity; etc. As to the driving sensation, reported were: Study of incidence factor of car sickness and the evaluation of a passenger`s feeling and his physiological responses; A study on evaluation of drowsiness; Experimental study on vigilance decline during a monotonous-driving simulation task; etc. In the computer soft relation, Development of ECU data acquisition and analysis support system; Development of software engineering system for automotive control system; etc. In addition, a lot of papers were read including the following: A study on the heat transfer performance improvement of condenser for automotive air conditioning system; A study for preventing corrosion for tube of aluminum oil coolers; A study of engine cooling fan.

  6. 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

  7. 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.

  8. Eighth experts meeting on environmental radioactivity monitoring: Technical and organisational means for an optimised measurement of ambient radioactivity in the environment of nuclear facilities

    International Nuclear Information System (INIS)

    1991-01-01

    The plant-specific emission monitoring and environmental monitoring near nuclear facilities are part of the items of the agreement between the EC and the IAEA, for mutual rapid information in the case of accidents. The lectures presented to the technical discussion meeting deal with the legal and technical aspects involved. Dispersion models, computer-aided dispersion models, computer-aided information systems and advanced programs as well as measuring techniques and results of the emission monitoring and environmental monitoring near nuclear facilities are the aspects of main interest discussed at the meeting. (DG) [de

  9. Report of the technical committee meeting 1997 annual workshop on ASSET experience and feedback

    International Nuclear Information System (INIS)

    1997-01-01

    Papers and presentations were made by all participating countries and provided a wide range of perspectives on the use of the ASSET methodology. Generally, the views expressed were positive, however, there were comments on areas were the service could be improved or enhanced. The workshop was divided into three task groups to analyze the self-assessments conducted at Krsko NPP, Slovenia; Dukovany NPP, Czech Republic; and Balakovo NPP, Russian Federation. In addition, they were asked to comment on the recommendations on the ASSET service made by the Consultants' Meeting of 26-30 August 1996 on ''Performance of the IAEA programme on Operational Safety Services''. A presentation was made by Mr. B. Thomas to remind delegates of the ASSET methodologies, and Mr. V. Sivokon demonstrated the latest developments of computer software available for assisting in the plant Self-Assessment process. Refs, figs, tabs

  10. 33rd annual technical meeting of the Petroleum Society of CIM

    Energy Technology Data Exchange (ETDEWEB)

    1982-03-01

    This meeting report of a conference on 'Energy Self-Sufficiency: Dream or Reality.' to be held in Calgary June 6-9, 1982 gives details of the program and contains abstracts of the 99 papers. Ten of these concern coal. Topics include temperature and cavity configuration modelling associated with moving boundary in underground coal conversion; modelling of underground coal gasification; coal liquefaction heat transfer coefficients; viscosity of coal-bitumen and coal-anthracene oil slurries; economic extraction of methane through coal demethanation; coal and solid waste burning Stirling engines; Canadian program for underground coal conversion; effect of moisture on the behaviour of shales and roof bolt anchoring capacity; effect of weak floor interaction on stability of coal pillars; and pressures in coal silos.

  11. Report of the technical committee meeting 1997 annual workshop on ASSET experience and feedback

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

    Papers and presentations were made by all participating countries and provided a wide range of perspectives on the use of the ASSET methodology. Generally, the views expressed were positive, however, there were comments on areas were the service could be improved or enhanced. The workshop was divided into three task groups to analyze the self-assessments conducted at Krsko NPP, Slovenia; Dukovany NPP, Czech Republic; and Balakovo NPP, Russian Federation. In addition, they were asked to comment on the recommendations on the ASSET service made by the Consultants` Meeting of 26-30 August 1996 on ``Performance of the IAEA programme on Operational Safety Services``. A presentation was made by Mr. B. Thomas to remind delegates of the ASSET methodologies, and Mr. V. Sivokon demonstrated the latest developments of computer software available for assisting in the plant Self-Assessment process. Refs, figs, tabs.

  12. 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.

  13. Meeting

    Indian Academy of Sciences (India)

    July 1989 No.19 Newsletter of the Indian Academy of Sciences. 55th Annual. Meeting ... in the world, keeping alive atthe same time his research interests, abreast .... theory made a comeback with many new ideas and with the success of the ...

  14. 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

  15. Steady-state operation of magnetic fusion devices: Plasma control and plasma facing components. Report on the IAEA technical committee meeting held at Fukuoka, 25-29 October 1999

    International Nuclear Information System (INIS)

    Engelmann, F.

    2000-01-01

    An IAEA Technical Committee Meeting on Steady-State Operation of Magnetic Fusion Devices - Plasma Control and Plasma Facing Components was held at Fukuoka, Japan, from 25 to 29 October 1999. The meeting was the second IAEA Techical Committee Meeting on the subject, following the one held at Hefei, China, a year earlier. The meeting was attended by over 150 researchers from 10 countries

  16. 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

  17. Molecular markers predicting radiotherapy response: Report and recommendations from an International Atomic Energy Agency technical meeting

    International Nuclear Information System (INIS)

    West, Catharine M.L.; McKay, Michael J.; Hoelscher, Tobias; Baumann, Michael; Stratford, Ian J.; Bristow, Robert G.; Iwakawa, Mayumi; Imai, Takashi; Zingde, Surekha M.; Anscher, Mitchell S.; Bourhis, Jean; Begg, Adrian C.; Haustermans, Karin; Bentzen, Soren M.; Hendry, Jolyon H.

    2005-01-01

    Purpose: There is increasing interest in radiogenomics and the characterization of molecular profiles that predict normal tissue and tumor radioresponse. A meeting in Amsterdam was organized by the International Atomic Energy Agency to discuss this topic on an international basis. Methods and Materials: This report is not completely exhaustive, but highlights some of the ongoing studies and new initiatives being carried out worldwide in the banking of tumor and normal tissue samples underpinning the development of molecular marker profiles for predicting patient response to radiotherapy. It is generally considered that these profiles will more accurately define individual or group radiosensitivities compared with the nondefinitive findings from the previous era of cellular-based techniques. However, so far there are only a few robust reports of molecular markers predicting normal tissue or tumor response. Results: Many centers in different countries have initiated tissue and tumor banks to store samples from clinical trials for future molecular profiling analysis, to identify profiles that predict for radiotherapy response. The European Society for Therapeutic Radiology and Oncology GENEtic pathways for the Prediction of the effects of Irradiation (GENEPI) project, to store, document, and analyze sample characteristics vs. response, is the most comprehensive in this regard. Conclusions: The next 5-10 years are likely to see the results of these and other correlative studies, and promising associations of profiles with response should be validated in larger definitive trials

  18. 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.

  19. 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

  20. 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.

  1. Falling chains

    OpenAIRE

    Wong, Chun Wa; Yasui, Kosuke

    2005-01-01

    The one-dimensional fall of a folded chain with one end suspended from a rigid support and a chain falling from a resting heap on a table is studied. Because their Lagrangians contain no explicit time dependence, the falling chains are conservative systems. Their equations of motion are shown to contain a term that enforces energy conservation when masses are transferred between subchains. We show that Cayley's 1857 energy nonconserving solution for a chain falling from a resting heap is inco...

  2. Results on Technical and Consultants Service Meetings on Lessons Learned from Operating Experience in Wet and Dry Spent Fuel Storage

    International Nuclear Information System (INIS)

    White, B.; Zou, X.

    2015-01-01

    Spent fuel storage has been and will continue to be a vital portion of the nuclear fuel cycle, regardless of whether a member state has an open or closed nuclear fuel cycle. After removal from the reactor core, spent fuel cools in the spent fuel pool, prior to placement in dry storage or offsite transport for disposal or reprocessing. Additionally, the inventory of spent fuel at many reactors worldwide has or will reach the storage capacity of the spent fuel pool; some facilities are alleviating their need for additional storage capacity by utilizing dry cask storage. While there are numerous differences between wet and dry storage; when done properly both are safe and secure. The nuclear community shares lessons learned worldwide to gain knowledge from one another’s good practices as well as events. Sharing these experiences should minimize the number of incidents worldwide and increase public confidence in the nuclear industry. Over the past 60 years, there have been numerous experiences storing spent fuel, in both wet and dry mediums, that when shared effectively would improve operations and minimize events. These lessons learned will also serve to inform countries, who are new entrants into the nuclear power community, on designs and operations to avoid and include as best practices. The International Atomic Energy Agency convened a technical and several consultants’ meetings to gather these experiences and produce a technical document (TECDOC) to share spent fuel storage lessons learned among member states. This paper will discuss the status of the TECDOC and briefly discuss some lessons learned contained therein. (author)

  3. Summary of Prioritized Research Opportunities. Building America Planning Meeting, November 2-4, 2010

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2011-02-01

    This report outlines the results of brainstorming sessions conducted at the Building America Fall 2010 planning meeting, in which research teams and national laboratories identified key research priorities to incorporate into multi-year planning, team research agendas, expert meetings, and technical standing committees.

  4. Advances in fuel pellet technology for improved performance at high burnup. Proceedings of a Technical Committee meeting

    International Nuclear Information System (INIS)

    1998-08-01

    The IAEA has recently completed two co-ordinated Research Programmes (CRPs) on The Development of Computer Models for Fuel Element Behaviour in Water Reactors, and on Fuel Modelling at Extended Burnup. Through these CRPs it became evident that there was a need to obtain data on fuel behaviour at high burnup. Data related o thermal behaviour, fission gas release and pellet to clad mechanical interaction were obtained and presented at the Technical Committee Meeting on Advances in Fuel Pellet Technology for Improved Performance at High Burnup which was recommended by the International Working Group on Fuel Performance and Technology (IWGFPT). The 34 papers from 10 countries are published in this proceedings and presented by a separate abstract. The papers were grouped in 6 sessions. First two sessions covered the fabrication of both UO 2 fuel and additives and MOX fuel. Sessions 3 and 4 covered the thermal behaviour of both types of fuel. The remaining two sessions dealt with fission gas release and the mechanical aspects of pellet to clad interaction

  5. Advances in control assembly materials for water reactors. Proceedings of a technical committee meeting held in Vienna, 29 November - 2 December 1993

    International Nuclear Information System (INIS)

    1995-07-01

    To obtain an overall picture of the current usage of control materials, research under way on new materials and to identify areas where materials are necessary to improve the safety, reliability and/or economics of water reactors, the IAEA convened a Technical Committee Meeting on Advances in Control Materials for Water Reactors. This meeting was recommended by the International Working Group on Fuel Performance and Technology and was held in Vienna from 29 November to 2 December 1993. Twenty-seven participants from twelve different countries attended the meeting and twelve papers were presented and are reproduced in these proceedings together with a summary of the meeting. A separate abstract was prepared for each of the papers. Refs, figs and tabs

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

    International Nuclear Information System (INIS)

    Chung, Hyun-Kyung

    2012-12-01

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

  7. Applications of Research Reactors Towards Research on Materials for Nuclear Fusion Technology. Proceedings of a Technical Meeting

    International Nuclear Information System (INIS)

    2013-11-01

    of materials under development for Generation IV concepts. International collaboration among MTRs and specialized facilities has been identified as integral to progress in fusion development as well as enhancing reactor utilization. This publication specifies which areas of research remain in the qualification of structural materials and components, and has detailed the characteristics of many research reactors and devices that can accomplish an important portion of these necessary studies. This publication is the outcome of two recent IAEA sponsored meetings under its programme to enhance the utilization and collaboration of research reactor and material test facilities: - Consultancy meeting on Role of Research Reactors in Materials Research for Nuclear Fusion Technology, 13-15 December 2010, IAEA, Vienna; - Technical meeting on Materials under High Energy and High Intensity Neutron Fluxes for Nuclear Fusion Technology, 27-29 June 2011, IAEA, Vienna. These meetings brought together representatives from MTRs, spallation neutron sources, multiple beam irradiation facilities, material scientists as well as fusion community representatives to discuss the current state of fusion research and to plot necessary studies and modes of research collaboration

  8. Comparison of best estimate methods for judging design margins of advanced water-cooled reactors. Proceedings of a IAEA technical committee meeting. Working material

    International Nuclear Information System (INIS)

    1994-01-01

    The objectives of the Technical Committee Meeting on Significance of design and Operational Margins for advanced Water Cooled Reactor Systems were: to provide an international forum for presentation and discussion of recent results on best estimate methods for judging design margins of mentioned reactors; to identify and describe the technical features of best estimate methods for predicting margins and to provide input for a status report on a comparison of best estimate methods for assessing margins in different countries and organisations. Participants from thirteen countries presented fifteen papers describing their methods, state of art and experiences. Each of those is presented here by a separate abstract

  9. Comparison of best estimate methods for judging design margins of advanced water-cooled reactors. Proceedings of a IAEA technical committee meeting. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

    The objectives of the Technical Committee Meeting on Significance of design and Operational Margins for advanced Water Cooled Reactor Systems were: to provide an international forum for presentation and discussion of recent results on best estimate methods for judging design margins of mentioned reactors; to identify and describe the technical features of best estimate methods for predicting margins and to provide input for a status report on a comparison of best estimate methods for assessing margins in different countries and organisations. Participants from thirteen countries presented fifteen papers describing their methods, state of art and experiences. Each of those is presented here by a separate abstract Refs, figs, tabs

  10. 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

  11. Advanced methods of process/quality control in nuclear reactor fuel manufacture. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    technical committee meeting. Upon invitation of the Government of Germany and Siemens AG, KWU/Advanced Nuclear Fuel GmbH the meeting was held in Lingen, Germany from 18 to 22 October 1999. In total, 19 papers from 10 countries were grouped into four sessions which covered new developments for control of process and product quality, their implementation and results obtained including new approaches to employee motivation.

  12. Advanced methods of process/quality control in nuclear reactor fuel manufacture. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2000-07-01

    technical committee meeting. Upon invitation of the Government of Germany and Siemens AG, KWU/Advanced Nuclear Fuel GmbH the meeting was held in Lingen, Germany from 18 to 22 October 1999. In total, 19 papers from 10 countries were grouped into four sessions which covered new developments for control of process and product quality, their implementation and results obtained including new approaches to employee motivation

  13. 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

  14. Annual International DIC Society Conference and SEM Fall Conference

    CERN Document Server

    Reu, Phillip

    2017-01-01

    This collection represents a single volume of technical papers presented at the Annual International DIC Society Conference and SEM Fall Conference organized by the Society for Experimental Mechanics and Sandia National Laboratories and held in Philadelphia, PA, November 7-10, 2016. The volume presents early findings from experimental, standards development and various other investigations concerning digital image correlation - an important area within Experimental Mechanics. The area of Digital Image Correlation has been an integral track within the SEM Annual Conference spearheaded by Professor Michael Sutton from the University of South Carolina. In 2016, the SEM and Sandia joined their collaborative strengths to launch a standing fall meeting focusing specifically on developments in the area of Digital Image Correlation. The contributed papers within this volume span numerous technical aspects of DIC including standards development for the industry. .

  15. First principles based transport theory. Report on the IAEA technical committee meeting held at Kloster Seeon, Germany, 21-23 June 1999

    International Nuclear Information System (INIS)

    Biskamp, D.; Nuehrenberg, J.; Diamond, P.H.; Garbet, X.; Lin, Z.; Rogers, R.N.

    2000-01-01

    This IAEA Technical Committee Meeting on plasma transport theory was organized jointly by the Max-Planck-Institute for Plasma Physics, Garching, and the IAEA, Vienna. It took place on 21-23 June 1999 in Kloster Seeon, Germany. The topics were: 1. Turbulent transport in the tokamak core plasma; 2. Turbulence suppression, shear amplification and transport bifurcation dynamics; 3. Turbulence transport in the tokamak edge plasma; 4. Global aspects of turbulent transport in tokamak plasmas; 5. Neoclassical transport, in particular in stellarators

  16. Proceedings of the sixth technical committee meeting organized by the IAEA and held in Vienna, Austria, 8-11 June 1987

    International Nuclear Information System (INIS)

    1987-01-01

    The Technical Committee on Thermal Reactor Safety Research held its sixth meeting from 8-11 June 1987 at the Agency's Headquarters in Vienna. It was attended by 25 participants representing 18 countries and 2 international organizations. With respect to exchange on national research activities the committee members presented their most recent achievements in the area of nuclear safety research. A separate abstract was prepared for each of their presentations. Refs, figs and tabs

  17. Unconventional options for plutonium disposition. Proceedings of a technical committee meeting held in Obninsk, Russian Federation, 7-11 November 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    This publication summarizes discussions and presents selected papers from a Technical Committee meeting that the IAEA convened in Obninsk, near Moscow, Russia, 7-11 November 1994 at the invitation of the Ministry of the Russian Federation on Atomic Energy, and which was hosted by the Institute of Physics and Power Engineering. The meeting focused on the disposition of plutonium produced from the operation of nuclear power plants in areas related to the nuclear fuel cycle. Plutonium is formed in all existing nuclear power plants and the unconsumed part remaining in spent fuel is a generic by-product of nuclear power generation. Over the next 15 to 20 years, a significant amount of plutonium will be produced in nuclear power stations worldwide, adding to amounts already in storage. Additionally, the world`s plutonium stocks are being affected by decisions concerning the management and utilization of plutonium recovered from nuclear weapons which are being dismantled. In this context, national strategies are directed at reducing the stockpiles of separated plutonium worldwide, and in further developing technologies capable of safely and securely using and handling plutonium. The purpose of the IAEA`s Technical Committee meeting was to consider unconventional approaches for plutonium disposition, both from the points of view of the fuel cycle as a whole and the specific types of nuclear fuel being used. The aims were to obtain technical descriptions of these approaches, engineering judgements on their technological status and development, and reports on national experience in this field. The meeting`s results and conclusions are providing valuable guidance for future activities in this subject area. Refs, figs and tabs.

  18. Summary of Prioritized Research Opportunities: Building America Program Planning Meeting, Washington, D.C., November 2-4, 2010

    Energy Technology Data Exchange (ETDEWEB)

    2011-02-01

    This report outlines the results of brainstorming sessions conducted at the Building America Fall 2010 planning meeting, in which research teams and national laboratories identified key research priorities to incorporate into multi-year planning, team research agendas, expert meetings, and technical standing committees.

  19. 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)

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

    International Nuclear Information System (INIS)

    Latge, C.

    1997-11-01

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

  1. 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.

  2. Report of 5th new nuclear fuel research meeting, Yayoi Research Group. Trend of advanced basic research in nuclear fuel technical development

    International Nuclear Information System (INIS)

    1994-03-01

    Theme of this meeting is 'Trend of advanced basic research in nuclear fuel technical development', and it was attempted to balance both sides of the basic research and the development. At the meeting, lectures were given on the chemical form of FPs in oxide fuel pins, the absorption of hydrogen of fuel cladding tubes, the application of hydride fuel to thorium cycle, the thermal properties of fuel cladding tubes, the preparation of NpN and heat conductivity, the high temperature chemical reprocessing of nitride fuel, the research on the annihilation treatment of minor actinide in fast reactors, the separation of TRU by dry process and the annihilation using a metallic fuel FBR. In this report, the summaries of the lectures are collected, and also the program of the meeting and the list of attendants are shown. (K.I.)

  3. Natural circulation data and methods for advanced water cooled nuclear power plant designs. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-04-01

    The complex set of physical phenomena that occur in a gravity environment when a geometrically distinct heat sink and heat source are connected by a fluid flow path can be identified as natural circulation (NC). No external sources of mechanical energy for the fluid motion are involved when NC is established. Within the present context, natural convection is used to identify the phenomena that occur when a heat source is put in contact with a fluid. Therefore, natural convection characterizes a heat transfer regime that constitutes a subset of NC phenomena. This report provides the presented papers and summarizes the discussions at an IAEA Technical Committee Meeting (TCM) on Natural Circulation Data and Methods for innovative Nuclear Power Plant Design. While the planned scope of the TCM involved all types of reactor designs (light water reactors, heavy water reactors, gas-cooled reactors and liquid metal-cooled reactors), the meeting participants and papers addressed only light water reactors (LWRs) and heavy water reactors (HWRs). Furthermore, the papers and discussion addressed both evolutionary and innovative water cooled reactors, as defined by the IAEA. The accomplishment of the objectives of achieving a high safety level and reducing the cost through the reliance on NC mechanisms, requires a thorough understanding of those mechanisms. Natural circulation systems are usually characterized by smaller driving forces with respect to the systems that use an external source of energy for the fluid motion. For instance, pressure drops caused by vertical bends and siphons in a given piping system, or heat losses to environment are a secondary design consideration when a pump is installed and drives the flow. On the contrary, a significant influence upon the overall system performance may be expected due to the same pressure drops and thermal power release to the environment when natural circulation produces the coolant flow. Therefore, the level of knowledge for

  4. Natural circulation data and methods for advanced water cooled nuclear power plant designs. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2002-04-01

    The complex set of physical phenomena that occur in a gravity environment when a geometrically distinct heat sink and heat source are connected by a fluid flow path can be identified as natural circulation (NC). No external sources of mechanical energy for the fluid motion are involved when NC is established. Within the present context, natural convection is used to identify the phenomena that occur when a heat source is put in contact with a fluid. Therefore, natural convection characterizes a heat transfer regime that constitutes a subset of NC phenomena. This report provides the presented papers and summarizes the discussions at an IAEA Technical Committee Meeting (TCM) on Natural Circulation Data and Methods for innovative Nuclear Power Plant Design. While the planned scope of the TCM involved all types of reactor designs (light water reactors, heavy water reactors, gas-cooled reactors and liquid metal-cooled reactors), the meeting participants and papers addressed only light water reactors (LWRs) and heavy water reactors (HWRs). Furthermore, the papers and discussion addressed both evolutionary and innovative water cooled reactors, as defined by the IAEA. The accomplishment of the objectives of achieving a high safety level and reducing the cost through the reliance on NC mechanisms, requires a thorough understanding of those mechanisms. Natural circulation systems are usually characterized by smaller driving forces with respect to the systems that use an external source of energy for the fluid motion. For instance, pressure drops caused by vertical bends and siphons in a given piping system, or heat losses to environment are a secondary design consideration when a pump is installed and drives the flow. On the contrary, a significant influence upon the overall system performance may be expected due to the same pressure drops and thermal power release to the environment when natural circulation produces the coolant flow. Therefore, the level of knowledge for

  5. Moving towards Ethnorelativism: A Framework for Measuring and Meeting Students' Needs in Cross-Cultural Business and Technical Communication

    Science.gov (United States)

    Wang, Junhua

    2013-01-01

    Scholars in business and technical communication have continuously made efforts to look for effective teaching approaches for cross-cultural business and technical communication; however, little research has been conducted to study the process by which students develop intercultural competence; fewer studies have been conducted to assess learners'…

  6. Meeting the Needs of Career and Technical Education: Observations from Graduates of a High School Health Science Program

    Science.gov (United States)

    Avey, Matthew R.

    2012-01-01

    Career and Technical education has been around for some time, and has often been shaped by the current economic landscape of the country. While current evolving trends focus on relevance for students in the school setting, a coexistence with college preparation curriculum is now the new trend in modern technical education. New programs have…

  7. Unconventional options for plutonium disposition. Proceedings of a technical committee meeting held in Obninsk, Russian Federation, 7-11 November 1994

    International Nuclear Information System (INIS)

    1995-11-01

    This publication summarizes discussions and presents selected papers from a Technical Committee meeting that the IAEA convened in Obninsk, near Moscow, Russia, 7-11 November 1994 at the invitation of the Ministry of the Russian Federation on Atomic Energy, and which was hosted by the Institute of Physics and Power Engineering. The meeting focused on the disposition of plutonium produced from the operation of nuclear power plants in areas related to the nuclear fuel cycle. Plutonium is formed in all existing nuclear power plants and the unconsumed part remaining in spent fuel is a generic by-product of nuclear power generation. Over the next 15 to 20 years, a significant amount of plutonium will be produced in nuclear power stations worldwide, adding to amounts already in storage. Additionally, the world's plutonium stocks are being affected by decisions concerning the management and utilization of plutonium recovered from nuclear weapons which are being dismantled. In this context, national strategies are directed at reducing the stockpiles of separated plutonium worldwide, and in further developing technologies capable of safely and securely using and handling plutonium. The purpose of the IAEA's Technical Committee meeting was to consider unconventional approaches for plutonium disposition, both from the points of view of the fuel cycle as a whole and the specific types of nuclear fuel being used. The aims were to obtain technical descriptions of these approaches, engineering judgements on their technological status and development, and reports on national experience in this field. The meeting's results and conclusions are providing valuable guidance for future activities in this subject area. Refs, figs and tabs

  8. 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)

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

    Science.gov (United States)

    Institute of Education Sciences, 2013

    2013-01-01

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

  10. Special section containing papers presented at the 13th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems (Beijing, China, 17-20 September 2013) Special section containing papers presented at the 13th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems (Beijing, China, 17-20 September 2013)

    Science.gov (United States)

    Lin, Z.

    2014-10-01

    In magnetic fusion plasmas, a significant fraction of the kinetic pressure is contributed by superthermal charged particles produced by auxiliary heating (fast ions and electrons) and fusion reactions (a-particles). Since these energetic particles are often far away from thermal equilibrium due to their non-Maxwellian distribution and steep pressure gradients, the free energy can excite electromagnetic instabilities to intensity levels well above the thermal fluctuations. The resultant electromagnetic turbulence could induce large transport of energetic particles, which could reduce heating efficiency, degrade overall plasma confinement, and damage fusion devices. Therefore, understanding and predicting energetic particle confinement properties are critical to the success of burning plasma experiments such as ITER since the ignition relies on plasma self-heating by a-particles. To promote international exchanges and collaborations on energetic particle physics, the biannual conference series under the auspices of the International Atomic Energy Agency (IAEA) were help in Kyiv (1989), Aspenas (1991), Trieste (1993), Princeton (1995), JET/Abingdon (1997), Naka (1999), Gothenburg (2001), San Diego (2003), Takayama (2005), Kloster Seeon (2007), Kyiv (2009), and Austin (2011). The papers in this special section were presented at the most recent meeting, the 13th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems, which was hosted by the Fusion Simulation Center, Peking University, Beijing, China (17-20 September 2013). The program of the meeting consisted of 71 presentations, including 13 invited talks, 26 oral contributed talks, 30 posters, and 2 summary talks, which were selected by the International Advisory Committee (IAC). The IAC members include H. Berk, L.G. Eriksson, A. Fasoli, W. Heidbrink, Ya. Kolesnichenko, Ph. Lauber, Z. Lin, R. Nazikian, S. Pinches, S. Sharapov, K. Shinohara, K. Toi, G. Vlad, and X.T. Ding. The conference program

  11. 17 April 2008 - Head of Internal Audit Network meeting visiting the ATLAS experimental area with CERN ATLAS Team Leader P. Fassnacht, ATLAS Technical Coordinator M. Nessi and ATLAS Resources Manager M. Nordberg.

    CERN Multimedia

    Mona Schweizer

    2008-01-01

    17 April 2008 - Head of Internal Audit Network meeting visiting the ATLAS experimental area with CERN ATLAS Team Leader P. Fassnacht, ATLAS Technical Coordinator M. Nessi and ATLAS Resources Manager M. Nordberg.

  12. 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...

  13. 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

  14. 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

  15. 42nd 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 42nd plenary on 8-12 April 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 dea...... were inter alia assessments of Mediterranean Sea stocks, future EU data collection, and technical measures.......The Scientific, Technical and Economic Committee for Fisheries hold its 42nd plenary on 8-12 April 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...

  16. Planning and management of uranium mine and mill closures. Proceedings of a technical committee meeting held in Liberec, Czech Republic, 3-6 May 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The Technical Committee Meeting on Planning and Management of Uranium Mine and Mill Closures was held in Liberec, Czech Republic from 3 to 6 May 1994. A total of 30 participants from nine countries attended the meeting. Nineteen papers were presented. Most of these papers dealt with the concept of and experiences in planning for and the subsequent decommissioning and rehabilitation of uranium mines and mills in Australia, Canada, Czech Republic, Germany, Romania, Slovenia, Spain and the USA. Two papers discussed the government`s role and relevant regulations related to the closures, decommissioning and remediation of uranium production facilities. Of particular interest to the participants was a non-technical paper presented by the Mayor of the city of Andujar, Spain, describing the negative political and socio-economic impacts associated with closure and decommissioning of an uranium mine/mill facility. The highlights of the meeting were the field visits to the uranium production facilities and rehabilitation programme sites of DIAMO and WISMUT companies, located respectively in Straz, Czech Republic and Koenigstein, Germany. Refs, figs and tabs.

  17. Factors determining the long term back end nuclear fuel cycle strategy and future nuclear systems. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2002-05-01

    The Technical Committee Meeting (TCM) was held in Vienna on 8-10 November 1999; it was organized by the International Atomic Energy Agency and attended by 26 participants from 16 Member States. The purpose of the meeting was to exchange information among experts on the back end fuel cycle strategies adopted by Member States; to identify key factors determining the long-term back end fuel cycle strategies; and to assess the applicability of these factors to future nuclear systems. Issues associated with the back end fuel cycle supporting a country's nuclear power programme are technical, economic, institutional and political. This TCM provided an opportunity to address these issues and their impacts to the back end fuel cycles, as well as to identify and assess factors affecting the back end fuel cycle strategies. The discussion was organized ib the following topical sessions: the nuclear fuel cycle; spent fuel management; waste management and repository; plutonium management. This document contains a summary of the meeting and 22 individual papers presented by participants. Each of the papers was indexed separately

  18. The assessment of occupational protection conditions in workplaces with high levels of exposure to natural radiation. Report from a technical committee meeting. Working material

    International Nuclear Information System (INIS)

    2002-01-01

    Occupational exposure from natural radiation is, in the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) 2000 Report, estimated to contribute to more than 80 percent of the world-wide annual collective dose from occupational exposure, uranium mining excluded. The Agency's Radiation Safety Standards Series, the Requirements, and the Safety Guides (jointly sponsored by the Agency and the International Labour Office), address the control of occupational exposures from natural sources of radiation. In addition, some Safety Reports on specific issues are in the process of being finalized. Following upon recommendations to the Agency from its Member States to provide further guidance on the control of occupational exposure to natural radiation, a Technical Committee Meeting on Assessment of Occupational Radiation Protection Conditions in Workplaces with High Levels of Exposure to Natural Radiation was held in Vienna from 7 to 11 May 2001. The objective of the meeting was to produce an inventory of problem areas, make an assessment of the problem and propose a draft work plan for the Agency, This IAEA Working Material includes the report from the meeting, including the presentations made. Based on the recommendations made by the Technical Committee, a work plan is being initiated, implying that more attention will be paid to occupational exposure from natural radiation sources in the Occupational Radiation Protection programme

  19. Factors determining the long term back end nuclear fuel cycle strategy and future nuclear systems. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-05-01

    The Technical Committee Meeting (TCM) was held in Vienna on 8-10 November 1999; it was organized by the International Atomic Energy Agency and attended by 26 participants from 16 Member States. The purpose of the meeting was to exchange information among experts on the back end fuel cycle strategies adopted by Member States; to identify key factors determining the long-term back end fuel cycle strategies; and to assess the applicability of these factors to future nuclear systems. Issues associated with the back end fuel cycle supporting a country's nuclear power programme are technical, economic, institutional and political. This TCM provided an opportunity to address these issues and their impacts to the back end fuel cycles, as well as to identify and assess factors affecting the back end fuel cycle strategies. The discussion was organized ib the following topical sessions: the nuclear fuel cycle; spent fuel management; waste management and repository; plutonium management. This document contains a summary of the meeting and 22 individual papers presented by participants. Each of the papers was indexed separately.

  20. Technical Targets - A Tool to Support Strategic Planning in the Subsurface Contaminants Focus Area

    International Nuclear Information System (INIS)

    Looney, B.B.

    2002-01-01

    The Subsurface Contaminants Focus Area (SCFA) is supported by a lead laboratory consisting of technical representatives from DOE laboratories across the country. This broadly representative scientific group has developed and implemented a process to define Technical Targets to assist the SCFA in strategic planning and in managing their environmental research and development portfolio. At an initial meeting in Golden Colorado, an initial set of Technical Targets was identified using a rapid consensus based technical triage process. Thirteen Technical Targets were identified and described. Vital scientific and technical objectives were generated for each target. The targets generally fall into one of the following five strategic investment categories: Enhancing Environmental Stewardship, Eliminating Contaminant Sources, Isolating Contaminants, Controlling Contaminant Plumes, Enabling DOEs CleanUp Efforts. The resulting targets and the detail they comprise on what is, and what is not, needed to meet Environmental Management needs provide a comprehensive technically-based framework to assist in prioritizing future work and in managing the SCFA program

  1. Technical meeting on lessons learned with respect to SAT implementation, including development of trainers and use of cost effective training methods

    International Nuclear Information System (INIS)

    2002-01-01

    The past years have brought some significant changes in the world energy market, where the nuclear power plants and utilities are operating. Part of NPPs is privatised now; the electricity markets are liberalized and become more and more international. Due to the increase of competition, the power production costs are now monitored more closely than before. The opening of electricity markets has led the nuclear power plants to be under the serious economic pressure with a demand for continuous cost reduction. All these require from NPPs to make their personnel training more cost-effective. In addition, based on modern technology, a great amount of new training tools, aids and technologies have been introduced during the last 2-3 years, these new opportunities can be quite useful for training cost optimization. On the basis of experience gained worldwide in the application of the systematic approach to training (SAT), SAT based training is now a broad integrated approach emphasizing not only technical knowledge and skills but also human factor related knowledge, skills and attitudes. In this way, all competency requirements for attaining and maintaining personnel competence and qualification can be met, thus promoting and strengthening quality culture and safety culture, which should be fostered throughout the initial and continuing training programmes. The subject of the present technical meeting was suggested by the members of the Technical Working Group on Training and Qualification of NPP Personnel (TWG-T and Q) and supported by a number of the IAEA meetings on NPP personnel training. The technical Meeting on 'Lessons Learned with Respect to SAT Implementation, Including Development of Trainers and Use of Cost Effective Training Methods' was organized by the IAEA in co-operation with the Tecnatom A.S. and was held from 21 to 24 October 2002 in San Sebastian de los Reyes/ Madrid, Spain. The main objective of the meeting was to provide an international forum for

  2. Technical committee meeting on Liquid Metal Fast Reactor (LMFR) developments. 33rd annual meeting of the International Working Group on Fast Reactors (IWG-FR). Working material

    International Nuclear Information System (INIS)

    2000-01-01

    Over the past 33 years, the IAEA has actively encouraged and advocated international cooperation in fast reactor technology. The present publication contains information on the status of fast reactor development and on worldwide activities in this advanced nuclear power technology during 1999/2000, as reported at the 33. annual meeting of the International Working Group on Fast Reactors. It is intended to provide information regarding the current status of LMFR development in IAEA Member States

  3. Annual meeting on nuclear technology '88. Technical session on focal points of the atomic energy law and the radiation protection law in 1988

    International Nuclear Information System (INIS)

    1988-06-01

    This issue of Annual Meeting on Nuclear Technology reports presents the papers of the technical session on 'Focal points of the atomic energy law and the radiation protection law in 1988'. The titles are: Is there a binding link between decisions of the atomic energy authority and criminal law? Conclusions to be drawn from the Alkem case court decision. - Recent developments in atomic energy law. - Current radiation protection law. - Codetermination at plant level in a nuclear installation. - The legal position of foreigners from neigbour countries in the field of atomic energy law. The licensing of nuclear installations near the border. (RST) [de

  4. Changes and events in uranium deposit development, exploration, resources, production and the world supply-demand relationship. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-09-01

    This report consists of the proceedings of the Technical Committee Meeting on Recent Changes and Events in Uranium Deposit Development, Exploration, Resources, Production and the World Supply/Demand Relationship, held in co-operation with the OECD Nuclear Energy Agency (OECD/NEA) in Kiev, Ukraine, from 22 to 26 May 1995. Some of the information from this meeting was also used in preparation of the 1995 edition of ''Uranium - Resources, Production and Demand'' a joint report by the OECD/NEA and the IAEA. At the Beginning of 1995 there were 432 nuclear power plants in operation with a combined electricity generating capacity of 340 GW(e). This represents nearly a 100% increase over the last decade. In 1995 over 2228 TW·h of electricity were generated, equivalent to about 17% of the world's total electricity. To achieve this, about 61,000 t U were required as nuclear fuel. For about a decade and a half uranium production and related activities have been decreasing because of declining uranium prices. For many participants in the nuclear industry there has been little interest in uranium supply because of the oversupplied market condition. The declining production led to the development of a supply and demand balance were production is currently meeting a little over 50% of reactor requirements and the excess inventory is being rapidly drawn down. This very unstable relationship has resulted in great uncertainty about the future supply or uranium. One of the objectives of this Technical Committee meeting was to bring together specialists in the field of uranium supply and demand to collect information on new developments. This helps provide a better understanding of the current situation, as well as providing information to plan for the future. Refs, figs, tabs

  5. 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

  6. 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...

  7. U.S. Army Hybrid Propulsion System R&D Overview ATA/Technology & Maintenance Council 2011 Fall Meeting, Hybrid Powertrain Task Force Session

    Science.gov (United States)

    2011-09-19

    and CVTS – HHO Technology – Start-Stop & Idle Stop Accessories – Pulse Jet Air Cleaner Ultra – Hybrid Energy Module (HEM) for Electric and Hybrid...The engine will meet 2010 EPA emission requirements – Hybrid drive powertrain; a 160 Horsepower (Hp) electric machine used for propulsion and

  8. 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

  9. 40th Plenary Meeting Report of the Scientific, Technical and Economic Committee for Fisheries (PLEN-12-02)

    DEFF Research Database (Denmark)

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

    The Scientific, Technical and Economic Committee for Fisheries hold its 40th plenary on 9-13 July 2012 in Copenhagen (Denmark). 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...

  10. 39th Plenary Meeting Report of the Scientific, Technical and Economic Committee for Fisheries (PLEN-12-01)

    DEFF Research Database (Denmark)

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

    The Scientific, Technical and Economic Committee for Fisheries hold its 39th plenary on 16-20 April 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...

  11. Moving forward on strengthening and sustaining National Immunization Technical Advisory Groups (NITAGs) globally: Recommendations from the 2nd global NITAG network meeting.

    Science.gov (United States)

    MacDonald, Noni E; Duclos, Philippe; Wichmann, Ole; Henaff, Louise; Harnden, Anthony; Alshammary, Aisha; Tijerino, Roberto Arroba; Hall, Madeline; Sacarlal, Jahit; Singh, Rupa Rajbhandari

    2017-12-15

    National Immunization Technical Advisory Groups (NITAGs) provide independent, evidence-informed advice to assist their governments in immunization policy formation. This is complex work and many NITAGs face challenges in fulfilling their roles. Inter-country NITAG collaboration opportunities have the potential to enhance NITAG function and grow the quality of recommendations. Hence the many requests for formation of a network linking NITAGs together so they can learn from each other. The first Global NITAG Network (GNN) meeting, held in 2016, led to a push to launch the GNN and grow the network. At the second GNN meeting, held June 28-29, 2017 in Berlin, the GNN was formally inaugurated. Participants discussed GNN governance, reflected on the April 2017 Strategic Advisory Group of Experts (SAGE) on Immunization conclusions concerning strengthening of NITAGs and also shared NITAG experiences in evaluation and inter-country collaborations and independence. They also discussed the role of Regional Technical Advisory Groups on Immunization (RTAGs) and regional networks. A number of issues were raised including NITAGs and communications, dissemination of recommendations and vaccine implementation as well as implications of off-label recommendations. Participants were alerted to immunization evidence assessment sites and value of sharing of resources. They also discussed potential GNN funding opportunities, developed an action plan for 2017-18 and selected a Steering Committee to help move the GNN forward. All participants agreed on the importance of the GNN and the value in attracting more countries to join the GNN. Copyright © 2017.

  12. EDITORIAL: Special issue containing papers presented at the 11th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems Special issue containing papers presented at the 11th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems

    Science.gov (United States)

    Kolesnichenko, Ya.

    2010-08-01

    The history of fusion research resembles the way in which one builds skyscrapers: laying the first foundation stone, one thinks about the top of the skyscraper. At the early stages of fusion, when it became clear that the thermonuclear reactor would operate with DT plasma confined by the magnetic field, the study of the `top item'—the physics of 3.5 MeV alpha particles produced by the DT fusion reaction—was initiated. The first publications on this topic appeared as long ago as the 1960s. At that time, because the physics of alpha particles was far from the experimental demand, investigations were carried out by small groups of theoreticians who hoped to discover important and interesting phenomena in this new research area. Soon after the beginning of the work, theoreticians discovered that alpha particles could excite various instabilities in fusion plasmas. In particular, at the end of the 1960s an Alfvén instability driven by alpha particles was predicted. Later it turned out that a variety of Alfvén instabilities with very different features does exist. Instabilities with perturbations of the Alfvénic type play an important role in current experiments; it is likely that they will affect plasma performance in ITER and future reactors. The first experimental manifestation of instabilities excited by superthermal particles in fusion devices was observed in the PDX tokamak in 1983. In this device a large-scale instability—the so called `fishbone instability'—associated with ions produced by the neutral beam injection resulted in a loss of a large fraction of the injected energy. Since then, the study of energetic-ion-driven instabilities and the effects produced by energetic ions in fusion plasmas has attracted the growing attention of both experimentalists and theorists. Recognizing the importance of this topic, the first conference on fusion alpha particles was held in 1989 in Kyiv under the auspices of the IAEA. The meeting in Kyiv and several

  13. Support for a special symposium to highlight the research of early career women physical chemists at the 2011 fall ACS nationall meeting, Aug 28-Sept

    Energy Technology Data Exchange (ETDEWEB)

    Richmond, Geraldine [Univ. of Oregon, Eugene, OR (United States)

    2012-12-19

    The symposium was well attended during the 4-day symposium. The invited speakers were primarily women in early career stage (~4-8 years) with a few senior women and men as invited speakers or session chairs. Included in each day was a Poster Session for graduate students and a lunch in which the turn out was strong and the posters presented encouraged much of dialogue with the invited speakers, guests and others attending the ACS meeting and wanted to discuss the student's research and meet with the speakers. Most all speakers and participants were very positive about the sessions and expressed that the funding to cover some expenses made it possible for them to attend the conference and the poster session luncheon. There was a total of 51 presenters, below are the speakers and their abstracts, in order presented:

  14. International Atomic Energy Agency Technical Committee Meeting, Innovative approaches to fusion energy, Pleasanton, CA, October 20-23, 1997

    International Nuclear Information System (INIS)

    Perkins, L. J.

    1997-01-01

    The Purpose of this Meeting is to provide a forum for discussion of approaches to fusion other than conventional tokamaks and stellarators, such as: (1) quasi-steady-state systems (mirrors, RFP's, spheromaks, FRC'S, spherical tori,...); (2) short-pulsed systems (liners, Z-pinch variants, plasma foci, novel ICF, ...); and (3) fusion technology innovations

  15. 77 FR 2924 - Notice of Public Meeting and Request for Comment on the Branch Technical Position on the Import...

    Science.gov (United States)

    2012-01-20

    ... phrase ``Of U.S. origin'' to the first exclusion to the definition of ``radioactive waste'' in Sec. 110.2...'' exclusion. The staff is holding a public meeting to obtain comments from stakeholders on the draft BTP and... practical to do so. NRC plans to consider these stakeholder views in the development of a revised draft BTP...

  16. 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...

  17. 77 FR 12354 - Meeting of the Joint Forum on Environmental Technical Cooperation Pursuant to the United States...

    Science.gov (United States)

    2012-02-29

    ... the subject line ``United States-Jordan Joint Forum Meeting.'' If you have access to the Internet, you... promote sustainable economic growth and development. The plan outlined activities to, among other things... laws through, among other things, the promotion of economic opportunities, voluntary measures to...

  18. Safe handling, transport and storage of plutonium. Proceedings of a technical committee meeting held in Vienna, 18-21 October 1993

    International Nuclear Information System (INIS)

    1994-10-01

    Plutonium inventories and utilization rates worldwide are growing. It is important for nuclear power programmes everywhere that no incidents or accidents with plutonium occur. It is therefore important that all who deal with plutonium, do so safely. All those who deal with plutonium should have available the best information on safety handling and storage. Several countries have mature plutonium programmes. However, information exchange on plutonium has been limited. This has precluded the development until now of consensus documentation on safe handling and storage of plutonium. The Technical Committee has been established to address these problems and this Technical Document is the first product in this process. The purpose of the meeting was to bring together experts with significant experience in handling, transporting and storing plutonium; to exchange information and experiences dealing with plutonium at their facilities; to describe their practices (guidelines, procedures, regulations, etc.) for safely dealing with plutonium; to assess the need to develop and publish a consensus plutonium safety practices document(s), and to recommend possible future IAEA activities in this technical area. Refs, figs and tabs

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

    International Nuclear Information System (INIS)

    2003-11-01

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

  20. 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...

  1. Annual meeting on nuclear technology '85. Technical session on nuclear power plant simulators. Jahrestagung Kerntechnik '85. Fachsitzung Simulatoren bei Kernkraftwerken

    Energy Technology Data Exchange (ETDEWEB)

    1987-01-01

    The ten lectures read at this Technical Session deal with nuclear power plant simulators and their functions for the training of control room personnel, with test facilities for analysis and simulation of incidents and the relevant plant behaviour, and with the computer codes for fast simulation of reactor processes. The papers explain in particular the HAMMLAB project, the COSIMA fast core simulator, and the OPAL simulator for the KWU convoy process information system named PRINS.

  2. 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....

  3. Recent developments in uranium resources and supply. Proceedings of a technical committee meeting held in Vienna, 24-28 May 1993

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    In recent years substantial uncertainties regarding uranium supply have made it very difficult for both uranium producers and users to plan for the future. In 1992 uranium production met only about 63 percent of reactor requirements. This resulted in a very unstable supply/demand balance where inventory drawdown (supplemented by minor amounts of reprocessing) filled the 20,960 tonne shortfall. The IAEA convened this Technical Committee meeting to take advantage of the new opportunities to collect and analyse information related to the future supply and demand balance and to help reduce uncertainties regarding the relationship. The meeting was effective in bringing together experts from all regions to share, exchange and disseminate information regarding uranium related activities. This meeting on Recent Developments in Uranium Resources and Supply was held in Vienna from 24 to 26 May 1993. It was attended by 47 participants from 23 countries. Twenty-one papers were presented. Contributions from China, the Czech Republic, India, Kazakhstan, Mongolia, Romania and the Russian Federation represent new information in this field. Refs, figs and tabs.

  4. SEG international exposition and sixty-fourth annual meeting -- 1994 Technical program: Expanded abstracts with authors' biographies

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    The papers presented at the meeting are arranged into the following sections: Borehole geophysics; Computing techniques; Development and production geophysics; Electromagnetics; Gravity and magnetics; Interpretation methods and case histories; Mining geophysics; Near-surface geophysics; Poster presentations; Seismic acquisition; Seismic inversion; Seismic lithology; Seismic modeling and migration; Seismic processing; and a workshop on Seismic data acquisition and processing in mountainous thrust areas. 266 papers have been processed separately for inclusion on the data base

  5. Advances in applications of burnup credit to enhance spent fuel transportation, storage, reprocessing and disposition. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2007-05-01

    Given a trend towards higher burnup power reactor fuel, the IAEA began an active programme in burnup credit (BUC) with major meetings in 1997 (IAEA-TECDOC-1013), 2000 (IAEA-TECDOC-1241) and 2002 (IAEA-TECDOC-1378) exploring worldwide interest in using BUC in spent fuel management systems. This publication contains the proceedings of the IAEA's 4th major BUC meeting, held in London. Sixty participants from 18 countries addressed calculation methodology, validation and criticality, safety criteria, procedural compliance with safety criteria, benefits of BUC applications, and regulatory aspects in BUC. This meeting encouraged the IAEA to continue its activities on burnup credit including dissemination of related information, given the number of Member States having to deal with increased spent fuel quantities and extended durations. A 5th major meeting on burnup credit is planned 2008. Burnup credit is a concept that takes credit for the reduced reactivity of fuel discharged from the reactor to improve loading density of irradiated fuel assemblies in storage, transportation, and disposal applications, relative to the assumption of fresh fuel nuclide inventories in loading calculations. This report has described a general four phase approach to be considered in burnup credit implementation. Much if not all of the background research and data acquisition necessary for successful burnup credit development in preparation for licensing has been completed. Many fuel types, facilities, and analysis methods are encompassed in the public knowledge base, such that in many cases this guidance will provide a means for rapid development of a burnup credit program. For newer assembly designs, higher enrichment fuels, and more extensive nuclide credit, additional research and development may be necessary, but even this work can build on the foundation that has been established to date. Those, it is hoped that this report will serve as a starting point with sufficient reference to

  6. Preprint of the Fall 1997 JSAE (Japan Society of Automotive Engineers) Meeting Science Lecture. No. 975; Jidosha gijutsukai 1997 nen shuki taikai gakujutsu koenkai maezurishu. 975

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

    No. 975 preprint of the Fall 1997 JSAE was summarized. As for the engine development, papers were made public on a study of reciprocating engine with Z mechanism, the combustion control system, etc. Attention was paid to internal combustion engine-electricity hybrid systems in terms of global warming prevention, and a study was made of environmental improvement effects by introducing next-generation automobiles. Image analysis and computer utilization in the structural design were also described. As to diesel engines, the combustion system and the exhaust gas problem were much studied. Also made were flow analysis on air conditioning and evaluation on the indoor thermal environment. Concerning the manufacturing process and materials, a lot of improvements were made public on thermal fatique resistance, reinforced materials, adoption of ceramics, corrosion resistance/wear resistance, etc. Operability and human engineering, and dynamics and safety are also important themes. Relating to the fuel, low fuel comsumption and additives were studied. The paper reported transmissions and the control systems, torque-transmitting mechanism, frictional property, etc. Especially, research/development were also much made of friction/wear resistant materials. ed and developed

  7. 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

  8. Proceedings (slides, posters) of the 7. IAEA Technical Meeting on Control, Data Acquisition, and Remote Participation for Fusion Research

    International Nuclear Information System (INIS)

    2009-01-01

    The main objective of this meeting is to present and discuss new developments and perspectives in the areas of control, data acquisition and remote participation for nuclear research around the world. The following topics have been covered: 1) plasma control, 2) machine control, monitoring, safety and remote manipulation, 3) data acquisition and signal processing, 4) database techniques for information storage and retrieval, 5) advanced computing and massive data analysis, 6) remote participation and virtual laboratory, 7) fast network technology and its application, and 8) ITER

  9. 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

  10. 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.

  11. 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.

  12. Progress in design, research and development and testing of safety systems for advanced water cooled reactors. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1996-04-01

    The meeting covered the following topics: Developments in design of safety-related heat removal components and systems for advanced water cooled reactors; status of test programmes on heat removal components and systems of new designs; range of validity and extrapolation of test results for the qualification of design/licensing computer models and codes for advanced water cooled reactors; future needs and trends in testing of safety systems for advanced water cooled reactors. Tests of heat removal safety systems have been conducted by various groups supporting the design, testing and certification of advanced water cooled reactors. The Technical Committee concluded that the reported test results generally confirm the predicted performance features of the advanced designs. Refs, figs, tabs

  13. Progress in design, research and development and testing of safety systems for advanced water cooled reactors. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    The meeting covered the following topics: Developments in design of safety-related heat removal components and systems for advanced water cooled reactors; status of test programmes on heat removal components and systems of new designs; range of validity and extrapolation of test results for the qualification of design/licensing computer models and codes for advanced water cooled reactors; future needs and trends in testing of safety systems for advanced water cooled reactors. Tests of heat removal safety systems have been conducted by various groups supporting the design, testing and certification of advanced water cooled reactors. The Technical Committee concluded that the reported test results generally confirm the predicted performance features of the advanced designs. Refs, figs, tabs.

  14. Developing a Systematic Education and Training Approach Using Personal Computer Based Simulators for Nuclear Power Programmes. Proceedings of a Technical Meeting

    International Nuclear Information System (INIS)

    2018-01-01

    This publication compiles the output and findings of a technical meeting organized by the IAEA. The use of personal computer (PC) based basic principle simulators in education and training is aimed at enhancing understanding of nuclear technologies through “learning by doing”. This hands-on experiential training is highly suitable for operators, maintenance technicians, suppliers, regulators, students and engineers. Experts from 21 Member States, together with IAEA staff, presented the current status of the PC based basic principle simulators, their applications in education and training and identified relevant gaps and needs for improvements and/or new development. The resultant publication includes summaries of the presentations, follow-up discussions as well as conclusions and recommendations for possible future activities.

  15. Meeting energy demand in a developing economy without damaging the environment. A case study in Sabah, Malaysia, from technical, environmental and economic perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Koh, Siong Lee; Lim, Yun Seng [Department of Physical Science, Electrical and Electronic Engineering, Tunku Abdul Rahman University (Malaysia)

    2010-08-15

    The challenges faced by the developing countries are unique in that they need to meet the increasing energy demands for their economic growths at a competitive price without damaging the environments. In this paper, a case study on the electricity demand issue in Sabah, Malaysia, is presented to investigate potential solutions in addressing this current need for a typical developing economy from the technical, economical and environmental perspectives. Sabah, one of the 13 states in Malaysia, is currently experiencing a serious power shortage, especially at the east coast. A 300 MW coal plant is proposed by the electricity utility company. However, the proposal has been rejected in the past several years due to the negative environmental impacts of the plant. In this paper, a number of alternative solutions were evaluated and proposed with respect to the viability of technologies, financial return and minimum environmental impact in terms of GHG emission. (author)

  16. Meeting energy demand in a developing economy without damaging the environment-A case study in Sabah, Malaysia, from technical, environmental and economic perspectives

    International Nuclear Information System (INIS)

    Koh, Siong Lee; Lim, Yun Seng

    2010-01-01

    The challenges faced by the developing countries are unique in that they need to meet the increasing energy demands for their economic growths at a competitive price without damaging the environments. In this paper, a case study on the electricity demand issue in Sabah, Malaysia, is presented to investigate potential solutions in addressing this current need for a typical developing economy from the technical, economical and environmental perspectives. Sabah, one of the 13 states in Malaysia, is currently experiencing a serious power shortage, especially at the east coast. A 300 MW coal plant is proposed by the electricity utility company. However, the proposal has been rejected in the past several years due to the negative environmental impacts of the plant. In this paper, a number of alternative solutions were evaluated and proposed with respect to the viability of technologies, financial return and minimum environmental impact in terms of GHG emission.

  17. Technical committee meeting 'to produce draft topical documents on provisions for the application of the regulations for the safe transport of radioactive material'. Chairman's report

    International Nuclear Information System (INIS)

    Baekelandt, Luc

    2000-01-01

    In 1996 a new Edition of the IAEA Transport Regulations was published as ST-1. These Regulations have been re-issued in 2000 as TS-R-1 (ST-1, Revised) with only minor editorial changes. These Regulations have not entered into force yet (at the time of this publication) through their incorporation in the legally binding modal regulations; currently it is foreseen that the modal requirements will enter into force during 2001, with transitional periods ranging from zero to twelve months. Nevertheless, a revision process has been started that must lead to a new edition of the regulations in 2003, becoming actually effective in 2005. This document contains the conclusions and recommendations made by the Technical Committee at the meeting. It also contains the reports of the working groups, outlines of draft TECDOCs on radiation protection programmes and on transition from SS 6 to TS-R-1

  18. 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.

  19. June 1992 Hall B collaboation meeting

    International Nuclear Information System (INIS)

    Dennis, L.

    1992-01-01

    The Hall B collaboration meeting at the CEBAF 1992 Summer Workshop consisted of technical and physics working group meetings, a special beam line devices working group meeting the first meeting of the membership committee, a technical representatives meeting and a full collaboration meeting. Highlights of these meetings are presented in this report

  20. Impact of Fall Prevention on Nurses and Care of Fall Risk Patients.

    Science.gov (United States)

    King, Barbara; Pecanac, Kristen; Krupp, Anna; Liebzeit, Daniel; Mahoney, Jane

    2018-03-19

    Falls are common events for hospitalized older adults, resulting in negative outcomes both for patients and hospitals. The Center for Medicare and Medicaid (CMS) has placed pressure on hospital administrators by identifying falls as a "never event", resulting in a zero falls goal for many hospitals. Staff nurses are responsible for providing direct care to patients and for meeting the hospital no falls goal. Little is known about the impact of "zero falls" on nurses, patients and the organization. A qualitative study, using Grounded Dimensional Analysis (GDA) was conducted to explore nurses' experiences with fall prevention in hospital settings and the impact of those experiences on how nurses provide care to fall risk patients. Twenty-seven registered nurses and certified nursing assistants participated in in-depth interviews. Open, axial and selective coding was used to analyze data. A conceptual model which illustrates the impact of intense messaging from nursing administration to prevent patient falls on nurses, actions nurses take to address the message and the consequences to nurses, older adult patients and to the organization was developed. Intense messaging from hospital administration to achieve zero falls resulted in nurses developing a fear of falls, protecting self and unit, and restricting fall risk patients as a way to stop messages and meet the hospital goal. Results of this study identify unintended consequences of fall prevention message on nurses and older adult patients. Further research is needed understand how nurse care for fall risk patients.

  1. Using New Technologies for Design, Modernization and Automation of Systems and Processes Related with Nuclear Applications. Technical Report of an Experts' Meeting

    International Nuclear Information System (INIS)

    2016-04-01

    In recent years the International Atomic Energy Agency has organized a series of technical cooperation projects aimed at expanding and strengthening the capacities of laboratories that work with nuclear instrumentation, as well as developing prototypes of instruments and interfaces which can respond to different needs in nuclear applications in the Latin America Caribbean (RLA) region. The introduction of advanced technologies for the design of instrumentation, interfaces and devices specialized and for work automation systems or processes related nuclear applications, has enabled to make better use of the available instrumentation. Repair work and modernization are an alternative to counter the lack of maintenance services by equipment suppliers that exceed the time life provided by manufacturers (planned obsolescence). Not only do specialized designs allow to solve specific needs, but often help reduce costs and the deadlines of work. An expert' meeting was held under the regional project RLA1011 (Support Automation Systems and Processes in Nuclear Facilities) to prepare a technical report that would provide recommendations to Member States of the IAEA on the current state of development several advanced technologies and their main fields of application, including examples of work in the region within the framework of this project. Eleven analytics entirely in Spanish from participating Member States are included in this publication

  2. Innovations in uranium exploration, mining and processing techniques, and new exploration target areas. Proceedings of a technical committee meeting held in Vienna, 5-8 December 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    In 1994 there were 432 nuclear power plants in operation with a combined electricity generating capacity of 340 347 MWe. To achieve this, 58,000 tonnes of uranium were required as nuclear fuel. In view of its economic importance, the International Atomic Energy Agency has had a long-standing interest in uranium exploration, resources, production and demand. This is reflected in numerous publications covering different aspects of this field. Particularly worth mentioning is the periodical ``Uranium Resources, Production and Demand``, published jointly with the Nuclear Energy Agency of the OECD. Its fourteenth edition was published in early 1994. It was the objective of this Technical Committee meeting, the proceedings of which are presented in this TECDOC, to bring together specialists in the field and to collect information on new developments in exploration, mining techniques and innovative methods of processing that are more environmentally friendly. The meeting was attended by a total of 22 participants from 14 countries. Eleven papers were presented describing new exploration areas, improvements in processing methods, new mining techniques for the extraction of high grade ore, and innovative approaches for site reclamation. Two working groups were organized and dealt with the analysis of world uranium resources and the new direction of research in mining and ore processing. Refs, figs, tabs.

  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. Application of uranium exploration data and techniques in environmental studies. Proceedings of a technical committee meeting held in Vienna, 9-12 November 1993

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    Exploration for mineral commodities, uranium included normally utilizes extensive, systematic geophysical and geochemical surveys covering very large areas, often entire countries. This information represents a great wealth of data that could be used to produce baseline information for environmental studies and monitoring. It is with this appreciation that IAEA convened a Technical Committee meeting with the purpose of bringing together experts in uranium exploration, geophysics and geochemistry to discuss and exchange information on the benefits of past exploration data and commonly applied techniques in environmental studies. The meeting on the Use of Uranium Exploration Data and Techniques in Environmental Studies was attended by 44 participants from 23 countries and one international organization. Thirty-two papers covering case histories on the use of old uranium exploration data to prepare exposure dose rate and radon potential maps, the use of airborne gamma ray spectrometric systems to monitor nuclear power plants and nuclear fuel cycle facilities, and the use of similar systems in response to emergency measures in the case of accidental releases were presented. Refs, figs and tabs.

  5. Reliability of computerized safety systems at nuclear power plants. Report of a technical committee meeting held in Vienna, 21-25 June 1993

    International Nuclear Information System (INIS)

    1995-03-01

    Computer based technology is increasingly used in order to perform safety functions. In some recently designed nuclear power plants the whole safety system is computerized. In older plants replacement of conventional technology based system is seen to be of benefit. If the new technology is to be used, it must meet at least the same level of quality and reliability requirements as specified for conventional technology. However, there is a potential for enhancing the safety of nuclear power plants if the full power of computer technology is applied correctly through well designed, engineered and tested systems which are properly installed and maintained. It is essential that areas where reliability and quality can be improved are identified and that methods for assessing and assuring reliability are developed. The results of the Technical Committee Meeting on Reliability of Computerized Safety Systems at Nuclear Power Plants presented in this report are a step on the road to this goal of improved nuclear safety. Refs, figs and tabs

  6. Application of uranium exploration data and techniques in environmental studies. Proceedings of a technical committee meeting held in Vienna, 9-12 November 1993

    International Nuclear Information System (INIS)

    1995-10-01

    Exploration for mineral commodities, uranium included normally utilizes extensive, systematic geophysical and geochemical surveys covering very large areas, often entire countries. This information represents a great wealth of data that could be used to produce baseline information for environmental studies and monitoring. It is with this appreciation that IAEA convened a Technical Committee meeting with the purpose of bringing together experts in uranium exploration, geophysics and geochemistry to discuss and exchange information on the benefits of past exploration data and commonly applied techniques in environmental studies. The meeting on the Use of Uranium Exploration Data and Techniques in Environmental Studies was attended by 44 participants from 23 countries and one international organization. Thirty-two papers covering case histories on the use of old uranium exploration data to prepare exposure dose rate and radon potential maps, the use of airborne gamma ray spectrometric systems to monitor nuclear power plants and nuclear fuel cycle facilities, and the use of similar systems in response to emergency measures in the case of accidental releases were presented. Refs, figs and tabs

  7. Urban fall traps

    Directory of Open Access Journals (Sweden)

    Vera Lucia de Almeida Valsecchi

    2007-06-01

    Full Text Available Objectives: To evaluate the repercussion of falls in the elderly peoplewho live in the city of São Paulo and address - though synthetically- some questions regarding the city and its relation to aging and thequality of life of the elderly. Methods: This is a qualitative study. As fordata collection, “in-depth individual interviews” were applied. Selectionof subjects was guided by a procedure named as “network”. Results:Ten interviews were performed, nine with elderly individuals who werevictims of falls and one with a public authority representative. Dataresulting from interviews confirmed that significant changes occurin live of the elderly, who are victims of what has been called “urbantraps”, and that, by extrapolating mobility and dependence contexts,invade feelings, emotions and desires. The inappropriate environmentprovided by the city of São Paulo is confirmed by absence of adequateurban planning and lack of commitment of public authorities. It alsorevealed that the particular way of being old and living an elderlylife, in addition to right to citizenship, is reflected by major or lesserdifficulties imposed to the elderly to fight for their rights and have theirpublic space respected. Conclusion: The city of São Paulo is not anideal locus for an older person to live in. To the traps that are found inpublic places one can add those that are found in private places andthat contribute to the hard experience of falls among the elderly, anexperience that is sometimes fatal. In Brazil, the attention is basicallyfocused on the consequences of falls and not on prevention, by meansof urban planning that should meet the needs of the most vulnerablegroups - the physically disabled and the elderly.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-03-01

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

  9. Fall Protection Introduction, #33462

    Energy Technology Data Exchange (ETDEWEB)

    Chochoms, Michael [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-06-23

    The proper use of fall prevention and fall protection controls can reduce the risk of deaths and injuries caused by falls. This course, Fall Protection Introduction (#33462), is designed as an introduction to various types of recognized fall prevention and fall protection systems at Los Alamos National Laboratory (LANL), including guardrail systems, safety net systems, fall restraint systems, and fall arrest systems. Special emphasis is given to the components, inspection, care, and storage of personal fall arrest systems (PFASs). This course also presents controls for falling object hazards and emergency planning considerations for persons who have fallen.

  10. Cold from heat. 5th WAW Technical Meeting, Weinheim; Kaelte aus Waerme. 5. WAW-Fachtagung in Weinheim

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1998-09-01

    The Weiterbildungsakademie Weinheim (WAW) organised an interesting conference on the use of heat for refrigeration. Chaired by Dipl.-Ing. Eberhard Thne from the Institute for Energy Economy and Rational Utilisation of Energy of Stuttgart University the conference dealt with different applications and operating results of adsorption- and absorption refrigerators and direct-fuelled gas absorbers. Papers looked at different case studies such as refrigeration for Ikea Saarlouis, the district hospital in Heilbronn, the Federal Agency for Environmental Protection in Augsburg, Munich Airport or the Technical University of Berlin.(orig.). [Deutsch] Eine aeusserst praxisorientierte und interessante Fachtagung zum Thema Einsatz von Waerme fuer die Kaelteproduktion veranstaltete die Weiterbildungs-Akademie Weinheim (WAW) am 18. Juni dieses Jahres. Unter der Leitung von Dipl.-Ing. Eberhard Thoene vom Institut fuer Energiewirtschaft und Rationelle Energieanwendung der Universitaet Stuttgart wurden verschiedene Anwendungsbeispiele und Betriebsergebnisse zu Absorptions- und Adsorptions-Kaelteanlagen sowie direktbefeuerter Gasabsorber vorgestellt. Referiert wurde ueber die Kaelteversorgung so unterschiedlicher Objekte wie Ikea Saarlouis, das Kreiskrankenhaus Landkreis Heilbronn, das Landesamt fuer Umweltschutz in Augsburg, der Flughafen Muenchen oder die TU Berlin. (orig.)

  11. Status and risk assessment of the use of transgenic arthropods in plant protection. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2006-03-01

    New developments in the modern biotechnology have opened up the possibility of introducing genes into the germline of many insect species, including those of agricultural importance. This technology offers the potential to improve current pest control strategies that incorporate the Sterile Insect Technique (SIT). Potential improvements include the development of strains that (1) produce only male insects for sterilization and release and (2) carry a marker that distinguishes them from wild insects. There are many institutions involved in the development of transgenic insect technology both for studies on basic gene regulation and for the creation of transgenic strains for use in a wide range of insect control programmes. It has been realized that the release into the environment of transgenic insects will not be an easy process considering the current public sensitivities in this area. The fact that insects are mobile and that once released cannot be recalled creates much concern. If fertile transgenic insects were to be released in any type of control programme, then the transgene would enter the wild population through mating. This strategy is fraught with, as yet, unknown risks and it is inconceivable that regulatory approval will be given for such a release in the near future. However, when transgenic strains are integrated into a sterile insect release then the concerns about transmission of the transgene to the wild population disappear as the matings between the released and the wild insects are sterile. This scenario is likely to be the first type of transgenic release. Insects that are currently released in SIT programmes experience no significant regulatory problems, but this will not be the case if the insects that are released are transgenic, even if they are sterile. The meeting Status and Risk Assessment of the Use of Transgenic Arthropods in Plant Protection held in FAO Headquarters, Rome, in April 2002 was the first effort to bring together

  12. IAEA technical meeting on integrating analog and digital instrumentation and control systems in hybrid main control rooms at nuclear power plants. Book of abstracts

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    issues apply to new build projects as well. Technical experts and managers from the field of instrumentation and control, process control, human factors engineering, licensing, and computer applications are invited to a Technical Meeting dealing with all important aspects of control room modernization projects. The subject of the present technical meeting was suggested by the members of the IAEA Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG-NPPCI) and supported by a number of IAEA meetings on NPP I and C Systems. Additional information on the Technical Working Group, and on the activities of the IAEA Division of Nuclear Power is available on The purpose of the meeting is to provide an international forum for presentations and discussions of experience with various aspects of the integration of analog and digital instrumentation and control systems in hybrid main control rooms, as applicable to both existing plants and planned (or in-progress) new plant builds. Promising new technologies and future trends in development will be also discussed. The meeting is intended for experts and managers in the I and C field from nuclear power utilities, vendor companies, licensing bodies, research organizations and academic institutions.

  13. Nuclear energy acceptance and potential role to meet future energy demand. Which technical/scientific achievements are needed?

    Science.gov (United States)

    Schenkel, Roland

    2012-06-01

    recently been proposed for energy production, is critically reviewed. There are major challenges remaining that are shortly outlined. Scientific/technical achievements that are required in the light of the Fukushima accident are highlighted.

  14. Nuclear energy acceptance and potential role to meet future energy demand. Which technical/scientific achievements are needed?

    Energy Technology Data Exchange (ETDEWEB)

    Schenkel, Roland [European Commission, Joint Research Centre, Institute for Transuranium Elements, Hermann-von-Helmholtz-Platz 1,76344 Eggenstein-Leopoldshafen (Germany)

    2012-06-19

    have recently been proposed for energy production, is critically reviewed. There are major challenges remaining that are shortly outlined. Scientific/technical achievements that are required in the light of the Fukushima accident are highlighted.

  15. Experimental tests and qualification of analytical methods to address thermohydraulic phenomena in advanced water cooled reactors. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2000-05-01

    Technical Committee Meeting on Experimental Tests and Qualification of Analytical Methods to Address Thermohydraulic Phenomena in Advanced Water Cooled Reactors was convened to review the current status and the remaining needs in this field

  16. Project Experiences in Research Reactor Ageing Management, Modernization and Refurbishment. Report of a Technical Meeting on Research Reactor Ageing Management, Modernization and Refurbishment

    International Nuclear Information System (INIS)

    2014-08-01

    performance, or provide new products and services to existing or potential users and customers, as well as share information on the technical details of the work involved, will allow other organizations contemplating similar work to consider and better understand their own challenges. Such understanding can help to optimize future planning in terms of budget, schedule and resource expectations, and to enable informed decision making. The IAEA is working to systematically collect existing knowledge on research reactor ageing management, modernization and refurbishment to share within the community of reactor owners, operators and oversight authorities. To this end, experts from the research reactor community gathered at IAEA headquarters from 10–14 October 2011 for the Technical Meeting on Research Reactor Ageing, Modernization and Refurbishment. The outcomes of the meeting and the submissions of the participants are documented in this publication

  17. Project Experiences in Research Reactor Ageing Management, Modernization and Refurbishment. Report of a Technical Meeting on Research Reactor Ageing Management, Modernization and Refurbishment

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-08-15

    performance, or provide new products and services to existing or potential users and customers, as well as share information on the technical details of the work involved, will allow other organizations contemplating similar work to consider and better understand their own challenges. Such understanding can help to optimize future planning in terms of budget, schedule and resource expectations, and to enable informed decision making. The IAEA is working to systematically collect existing knowledge on research reactor ageing management, modernization and refurbishment to share within the community of reactor owners, operators and oversight authorities. To this end, experts from the research reactor community gathered at IAEA headquarters from 10–14 October 2011 for the Technical Meeting on Research Reactor Ageing, Modernization and Refurbishment. The outcomes of the meeting and the submissions of the participants are documented in this publication.

  18. Optimizing the CSP Tower Air Brayton Cycle System to Meet the SunShot Objectives - Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Bryner, Elliott [Soutwest Research Inst., San Antonio, TX (United States); Brun, Klaus [Soutwest Research Inst., San Antonio, TX (United States); Coogan, Shane [Soutwest Research Inst., San Antonio, TX (United States); Cunningham, C. Seth [Soutwest Research Inst., San Antonio, TX (United States); Poerner, Nathan [Soutwest Research Inst., San Antonio, TX (United States)

    2016-02-26

    The objective of this project is to increase Concentrated Solar Power (CSP) tower air receiver and gas turbine temperature capabilities to 1,000ºC by the development of a novel gas turbine combustor, which can be integrated on a megawatt-scale gas turbine, such as the Solar Turbines Mercury 50™. No combustor technology currently available is compatible with the CSP application target inlet air temperature of 1,000°C. Autoignition and flashback at this temperature prevent the use of conventional lean pre-mix injectors that are currently employed to manage NOx emissions. Additional challenges are introduced by the variability of the high-temperature heat source provided by the field of solar collectors, the heliostat in CSP plants. For optimum energy generation from the power turbine, the turbine rotor inlet temperature (TRIT) should remain constant. As a result of changing heat load provided to the solar collector from the heliostat, the amount of energy input required from the combustion system must be adjusted to compensate. A novel multi-bank lean micro-mix injector has been designed and built to address the challenges of high-temperature combustion found in CSP applications. The multi-bank arrangement of the micro-mix injector selectively injects fuel to meet the heat addition requirements to maintain constant TRIT with changing solar load. To validate the design, operation, and performance of the multi-bank lean micro-mix injector, a novel combustion test facility has been designed and built at Southwest Research Institute® (SwRI®) in San Antonio, TX. This facility, located in the Turbomachinery Research Facility, provides in excess of two kilograms per second of compressed air at nearly eight bar pressure. A two-megawatt electric heater raises the inlet temperature to 800°C while a secondary gas-fired heater extends the operational temperature range of the facility to 1,000°C. A combustor test rig connected to the heater has been designed and built to

  19. Seismic evaluation of existing nuclear power plants and other facilities V. 1. Proceedings of the technical committee meeting. Working material

    International Nuclear Information System (INIS)

    2002-01-01

    invited to fulfil the attached Technical Background Form

  20. Technical Meeting/Workshop on Topical Issues on Infrastructure Development: Managing the Development of a National Infrastructure for Nuclear Power Plants. Presentations

    International Nuclear Information System (INIS)

    2012-01-01

    The main purpose of the TM/Workshop is to provide an opportunity for exchange of specific information on the management of the development of a sustainable national infrastructure for Nuclear Power Plants as it is recommended in the Agency's Milestones approach. Taking into account the actual status of new nuclear power programmes in Member States, this Agency event shall focus on the moving beyond the consideration of the nuclear power and advancing to the next phase, when future partners (Consultants, NPP Vendors, EPC Contractors, etc.) shall be selected and contracted for the first Nuclear Power Plant. The objectives of the Technical Meeting/Workshop are the following: 1. To exchange specific information and to facilitate the management and coordination of the development and implementation of a national infrastructure for nuclear power; 2. To present and discuss case studies, good practices and lessons learned about recent experiences in implementing an appropriate infrastructure for nuclear power, including management methods and self-evaluation processes; 3. To allow participants to improve their knowledge of various aspects of nuclear infrastructure development; and 4. To provide a forum in which participants can discuss common challenges, opportunities for cooperation, concerns and issues their countries face in the infrastructure implementation process.